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Exam Rept 50-302/OL-85-04 on 851121-22.Exam Results:One Candidate Passed Oral Exam,Five of Seven Candidates Passed Written Reexam & One Candidate Passed Written Reexam of One Category
	ML20137Y281
Person / Time
Site:	Crystal River
Issue date:	01/29/1986
From:	Wilson B; NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
To:	;
Shared Package
ML20137Y272	List: ML20137Y268; ML20137Y281;
References
	50-302-OL-85-04, 50-302-OL-85-4, NUDOCS 8603120233
	Download: ML20137Y281 (102)
	v • d • e

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ENCLOSURE 1 l l

EXAMINATION REPORT 302/0L-85-04 Facility Licensee: Florida Power Corporation P. O. Box 14042, M.A.C. H-2 l St. Petersburg, FL 33733 Facility Narre: Crystal River 3 Facility Docket No.: 50-302 l Written and oral examinations were administered at Crystal River Nuclear Plant ,

near Crystal River Florida. l Chief Examiner: cs Bruct A. Wilson

. d.b m 2MfPC.

Uate Signed l Approved by: AM. u . .baw l!t 1[7d.

l Bruce A. Wilson, Section Chief Date 51gned Sumary:

Examinations on November 21 and 22,1985 An oral examination was administered to one candidate; The candidate passed.

Seven candidates were administered written ie-examinations of all categories; Five candidates passed. One candidate was administered a written reexamination of one category. The candidato passed.

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8603120233 960130 PDR ADOCK 03000302 PDR Y

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REPORT DETAILS

1. Facility Employees Contacted:

J. Alberdi, Manager-Site Nuclear Operations Technical Services

L. C. Kelley, Nuclear Operations Training Manager

R. C. Zareck, Nuclear Operations Instructor

Attended Exit Meeting

2. Examiners:

B. A. Wilson, NRC Region !!

! D. P. Falconer, NPC Region II

Chief Examiner

3. Examination Review At the conclusion of the written examinations, the examiners provided the facility with a copy of the written examinations and answer keys for review. The following comments were provided by the licensee by letter dated November 26, 1985,

a. Reactor Operator Examination (1) Question 1.5(c)

The answer on the key is correct, however, an increasing positive startup rate would also be indicative of a supercritical reactor.

RECOMMENDATION:

Accept " constant" or " increasing" for full credit.

Response: Question states "...several seconds af ter the reactivity addition is terminated."; therefore, only a constant startup rate is an acceptable answer.

j Resolution: No change to answer key.

(2) Question 1.10 i

I feel the answer "To prevent steam bubble formation in the head" should be adequite for full credit on this question. The pressur-izer response is a function of the steam bubble, not the cooldown rate.

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-_ . . , . - _ . _ _ _ _ _ . _ _ _ _ . _ _ _ - , _ , , _ . , . , _ . . . _ . _ _ ~ . .. _ _ , ,

_ _ . . - _ _ . . - _ - - _ - - - - _ . - . - . _ _ _ - - _ _ _ . . . - - - - _ ~ .-

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i RECOMMENDATION:

Accept "To prevent stean bubble fornation in the head" for full credit.

Response: "To prevent steam bubble fonnation in the head" is an acceptable answer for full credit.

} Resolution: Changed answer key to reflect reconinendation. ;

l (3) Question 2.10 (c)

J Excessive memorization. An operator is not expected to recall the power supply of all components at the MCC level. Nor is this

required of the operator per the R0 Job Analysis.

RECOMMENDATION:

i j Delete question from exam.

l Response: The intent of the question is to determine if candidates j know that SW pumps 2A and 2B are not powered from Engineered Safeguards MCC's.

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! Resolution: No change to question or answer key.

(4) 2:estion2.15(c) i . This is an irrelevant question. Under no conceivable circum-stances would an operator ever need to know, or even care, how i many heating elements are contained in a pressurizer heater i bundle, I

i l RECOMMENDATION:

Delete question from exam.

Response: Question was not adequately supported by NUREb 1122 K/A Catalog.

} Resolution: Deletedquestion2.15(c) j (5) Question 2.15 (d) i r This answer is correct, however, I feel "480V Plant Aux Dus" should also be accepted. AP-770, Pg. 5, Step 7, provides instructions for j reenergizing the pressurizer heaters from the B ES 4160 volt bus VIA j the 480V Plant Aux Bus, t

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3 RECOMMENDATION:

Accept "B" ES 4160 Volt Bus or 480 Volt Plant Aux Bus.

Response: A review of plant reference materials supports recommen-dation.

Resolution: Changed answer key to accept "480V Plant Aux. Bus" for full credit.

(6) Question 2.19 This question requires an unreasonable level of recollection.

RC Pump operation is infrequently performed and governed by a detailed step-by-step procedure. To expect an operator to recall from memory the details of every limit and precaution is unreason-able and counter productive.

RECOMMENDATION:

Delete question from exam.

Response: The limits and precautions for restart of a RCP are not provided in AP-380 and AP-380 does not direct the operator to an appropriate reference procedure; there-fore, we assume that this information is within the knowledge of the operator.

Resolution: No change to answer key.

(7) Question 3.1(4)

The answer "O psig" is identified as correct, however, "50 psig" could also be correct. To make "O psig" the only totally correct response the question should reference "TBV's not closed."

RECOMMENDATION:

Accept "O psig" or "50 psig" for full credit.

Response: A review of plant reference material supports this recomnienda tion.

Resolution: Changed answer key to reflect recommendation.

(8) Question 3.3(A)

Either the SG/RX Demand station or the ULD station could be correct answers depending on how f ar along in the startup the operator assumed he was.

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! RECOMMENDATION:

l l Accept "SG/RX Demand" or "ULD" for full credit.

l Response: A review of utility reference materials supports recom-

mendation.

l Resolution: Changed answer key to accept "ULD" or "SG/RX" station for full credit.

(9) Question 3.3(d.1) t Low Load and Startup control valves freeze when the MBV is not l closed.

RECOMMENDATION:

Accept " Control Valves" for full credit, t Response: A review of utility reference material supports recom-i mendation.

t Resolution: Changed answer key to also accept " Control Valves" for full credit.

(10) Questio,3.4 EFIC actuation A and B each send close signals to the Main Block Valves independently. If EFIC A and B are listed as separate signals, they should be accepted as correct.

RECOMMENDATION: ;

Accept EFIC A and EFIC B as separate answers.

Response: A review of utility reference material supports recomendation. I l

Resolution: Changed answer key to accept "EFIC A" or "EFIC B" actuation for full credit 1 (11) Question 3.7(a)

As installed, HP! blocks 3 and 4 (not 5) were required to set the RB Spray Permit. A subsequenf modification has removed the block 3 requirement. Only HPI block 4 is now necessary. This modification did not change the function or operation of the Permit and it is scheduled to be covered in an upcoming requal.

session. Some operators may be aware of this modification, uthers may not. I feel either " block 3 or 4" or " block 4" should be acceptable as correct. In any event, " block 3 and 5" l 1s incorrect.

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L RECOMMENDATION:

Accept either " Block 3 and 4" or " Block 4" for full credit.

Response: Reference material to support plant modification was not provided to support recorrrnendation to accept HPI Block 4 only for full credit. Indication of HPI Block 5 on the answer key was a typographical error.

Resolution: Changed answer key to "HPI Block 3 and 4".

(12) Question 3.10(a)

Three possible answers:

1. Bleed of f temp >_170*F.

2. Seal stage pressure drop >_2/3 RCS Pressure.

3. Loss of both seal injection and component cooling.

l RECOMMENDATION:

Accept any two for full credit.

l l Respons?: A review of utility reference material supports recom-l mendation.

Resolution: Changed answer key to also accept " Loss of both seal injection and component cooling" as one of l two correct answers.

l l (13) Questior 3.ll(c)

EFW would initiate. The Loss of All Reactor Coolant Pump actua-

tion cannot be bypassed until Rx power is (10%. By procedure.

l the bypass is remeved prior to reaching 20'D*F. At 450'F the bypass would not be in effect.

RECOMMENDATION:

l Delete question from exam.

Response: Question inappropriately referenced heatup instead of cooldown.

Resolution: DeletedQuestion3.ll(c) l l

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6 (14) Question 4.1(a)

This is a very confusing way to ask this question. The word

" identical" forces one to remember the steps word-for-word rather than through the memory dids many operators use to recall immedi-ate actions.

RECOMMENDATION:

Suggest that you reword this question for future use. No specific change recommended this time.

Response: None Resolution: No change was recomrrended.

(15) Question 4.1(c.tv) t The runback limit for 1 RC Pump is "a. 75%" '

t REC 0fEENDATION:

Accept "a. 75%" for full credit.

Response: AP-543 specifically states that the plant will stabilize q at approximately 70%. We recognize that the ICS lesson plan states 75%; therefore, if the procedure is incor-rect, it should be changed.

Resolution: No change to answer key.

(16) Question 4.2(a)

OP-502 is designed to fit several circumstances and therefore 4 lists several unnecessary steps that the operators may leave out.

Also, the specific sequence of the first 6 steps is not important as long as MANUAL is selected before SEQ-OR. The list should read:

1. ' Select MANUAL Select R00 Group Select ALL (optiunal)

Select AUX Select SEQ-OR Select J0G

2. Verify SYNC

! 3. Select CLAMP

4. Select MANUAL TRANSFER

5. Select CLAMP RELFASE i 6. Select GROUP j 7. Select RUN (if desired) i i

4 i 7 [

NOTE: Depressing TRANSFER RESET is not required in this situa-tion since you do not need to clear the transfer logic until you remove the rods from the AUX power supply.

RECOMMENDATION:

Accept some form of the~above for partial credit.

Response:~ A review of utility reference materials supports

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recommendation.

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I Resolution: Changed answer key to reflect recommendation.

j (17) 'Ouestion 4.7 i

j< This question does not ask the operator to state the plant sub-cooling margin requirements, therefore, " Loss of adequate subcool-

! ing margin" should be all that is required for full credit on this question. !

RECOMMENDATION:

Accept " Loss of adequate subcooling margin" for full credit.

Response: The Immediate Action-step includes the subcooling margin requirements. If the candidates do not state those l' requirements in their answers, we are unable to deter-mine if they know them.

Resolution: No change to answer key.

I (18) Question 4.9 This question is not reasonable. Many of the variables and allow-

! able deviations in the plant curve book are not linear with power.

To expect a man to recall the allowable deviation drawn on a curve from memory is not reasonable. An operator should be expected to be able to predict what vital parameters should be for various load levels, recognize if they vary from expected values, and use the curves or better yet, historical data to determine if they are within tolerance.

RECOMMENDATION:

Delete question from exam.

Response: An operator should be able to predict what vital param-eters should be for various loads and recognize if they vary from expected values. Question will not be deleted; however, full credit will'be given for answers ,

within established margin.

8 Resolution: Changed answer key .to give full credit for answers within 32 F or 2 psig of the setpoint and within 1 F or 1 psig of the tolerance.

(19) Question 4.14 The question specifically addresses (quotes) Immediate Action 1.

The answer key addresses Immediate Actions 1, 2, and 3. Only the valves listed in Immediate Action 1 should be required for full credit. In addition, a. steam line break on the "A" 0TSG could depressurize the "B" 0TSG due to the fact that they are cross connected thru the turbine steam chest with the plant on the line, or due to reverse heat transfer from the steam generator to the RCS as the primary loops cool down. Because'of this, it should be acceptable if an operator lists the isolation valves for both OTSG's rather than just one.

RECOMMENDATION:

Accept the valves listed for Immediate Action 1 for one or both OTSG's for full credit.

Response: MSV-55 is required to be closed manually by the opera-tor; therefore, we agree that it should not be included in the correct answer and also that OTSG "B" may be subject to depressurization.

Resolution: Deleted MSV-55 from answer key and changed answer key to accept valves on OTSG A or OTSG A and 0TSG B.

SENIOR REACTOR OPERATOR EXAMINATION (1) Question 5.3 Same comments and resolution as Question 1.10.

Response: Same as Question 1.10.

(2) Question 5.9(b)

This answer is TRUE. The steady state and transient limits for QPT are MORE restrictive for Power Range Channels than the Symmetrical Incore Detectors.

RECOMMENDATION:

Change correct answer to 'TRUE'.

Response: We agree with utility recommendation.

Resolution: Changed answer key to accept 'TRUE'.

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9 (3) Question 5.11 This question makes no sense as written. The word RATIO should' be deleted.

RECOMMENDATION:

Reword question prior to reuse. No specific change recommended here.

Response: No change requested.

(4) Question 5.14(D)

Increasing pump flow rate by opening the discharge valve should decrease NPSH, thereby INCREASING cavitation.

RECOMMENDATION:

Accept " INCREASING" for full credit.

Response: A review of utility reference material supports recommendation.

Resolution: Changed answer key to accept INCREASING.

(5) Questions 6.1 and 6.2 These two questions require excessive memorization of interlocks associated with infrequently used equipment. A fuel handling bridge has over 50 different interlocks. The major interlocks are tested by procedure (SP-532) when the bridges are in use. The operation of the bridge is governed by a procedure which is required to be maintained on the bridge with the operator. There is no reason an operator should be expected to recall from memory the interlocks associated with the bridge.

RECOMMENDATION:

Delete questions from exam.

Response: 10 CFR 55.22(h) states that senior operator written examinations will include questions on fuel handling facilities and procedures. Fuel handling interlocks are mechanisms utilized to prevent fuel damage during fuel handling operation and should be within the knowl-edge of the senior reactor operator. Also, NUREG-1122 lists ' fuel handling design features and interlocks at a sufficiently high importance rating.

10 A review of the reference material (STM-29 and FP-601) revealed the answer key to be incomplete. There are several additional interlocks which will be acceptable for credit in response to question 6.2.

Resolution: No change to . question or answer key for question 6.1 Accept additional interlocks for question 6.2 as per STM-21; Tables 3-3, 3-4, and 3-5.

(6) Question 6.8 Same comments and resolution as Question 2.19.

Response: Same as Question 2.19.

(7) Question 6.11(4)~

Same comments amd resolution as Question 3.1(4).

Response: Same as Question 3.1(4).

(8)'Ouestion6.13(a)

Same comments and resolution as Question 3.7(a).

Response: Same as Question 3.7(a).

(9) Question 6.15(c)

Same comments and resolution as question 3.11(c).

Response: Same as Question 3.11(c).

(10) Question 6.16(c)

The " Reactivity Alert" indicates either of two conditions:

I i 1. Rx tripped and all rods not in after 3 seconds.

2. Rx tripped and SR count rate ;t 1000 CPS af ter 25 minutes.

RECOMMENDATION:

Change answer key to' reflect correct answer above.

Response: A review of utility reference material supports

, recommendation.

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11 Resolution: Changed answer key to:

1. Rx tripped and all rods not in after 3 seconds.

2. Rx tripped and SR count ratelt1000 CPS af ter 25 minutes.

(11) Question 7.1 Answer should read LBPR Retainer and Source Retainer.

RECOMMENDATION:

Change the answer key to reflect correct answer above.

Response: Typographical error deleted 'and' from answer key.

Resolution: Changed answer key to accept LBPR retainer and source retainer.

(12) Question 7.4 This question requires detailed memorization of specific steps of a fuel handling procedure. Furthermore, the operation being called for is one rarely, if ever, done. The question is inappro-priate to an SR0 examination since it gives no indication of a man's ability to operate or direct the operation of the plant, RECOMMENDATION:

Delete question from exam.

Response: Question was not adequately supported by NUREG-1122, K/A Catalog.

Resolution: Delete Question 7.4 (13) Question 7.6 Same comments and resolution as Question 4.1.

Response: Same as Question 4.1.

(14) Question 7.10 Same comments and resolution as Question 4.9.

Response: Same as Question 4.9.

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-(15) Question 7.12 Requires memorization of specific steps _ of infrequently perfomed operating procedure.

RECOPMENDATION:

Delete question from exam.

Response: Question is designed to test the operator's knowledge of the system.

Resolution: No change to answer key.'

(16)' Ouestion 7.13 Same comments and resolution as Question 4.14.-

Response: Same as Question 4.14 (17) Question 7.14(a)'

Same comments and resolution as question 4.2(a).

Response: Same as Question 4.2(a).

(18) Question 8.17 No facility Coment

' Response: Knowledge of 10 CFR 50, Appendix J was required to answer the first part of the question.. Delete first blank and change point value to 0.5.

(19) Question 5.08 No facility comment Response: This question was deleted prior to the start of the examination since it was found to test the same learning objectives as Question 5.01.

4. Exit Meeting At the conclusion of the site visit, the examiners met with representatives of the plant staff to discuss the results of the examination. The individual who was administered the oral examination was identified as a clear pass on the. oral examination.

There were no generic weaknesses noted during the oral examination.

The . cooperation given to the examiners and the effort to ' ensure an atmosphere in the control room conducive to oral examinations was also noted and appreciated. '

The licensee did not identify as proprietary any of the material provided to or reviewed by the examiners.

OFFICIAL USE ONLY - PRIVACY ACT INFORMATION ENCLOSURE 2 POWER PLANT EXAMINATION RESULTS

SUMMARY

REQUAL ,

Total Passed Failed FACILITY ***g Results No. No. % No. %

Crvsta1 River 1. Reactor Operator DATE OF WRITTEN S.nor Op**'" Rea m Operatw I" "

11-21-85 5 3 60 2 40 [Sen o, op , , U DATE OF ORALS Reacts hatm r 33_97_qq p p lgg g q React O Retake DATE OF SIMULATOR Sin 91e Ro Cat 1 1 100 { ' g 'g" d*j2og ,,p,,,g,ng,,n, EXAMINERS Falconer / Wilson TYPE OF EXAM Requal s tD m oT)

"=.-/c=-

RO SRO TYPE 2 3 4 5 6 7 8 TOTAL NAME DOCKET NO- CODE 1 TOTAL W O S W O S Berostron, C. 4. 8226 96.0 35.7 79.2 79.z 82.5 Kirk. D. A. 7810 19_n q l .1 72 7 01 t- 00 7 Ka SPer. L . P. 8232 89.E Enningtnn_ n R G,107 64.6 G5.7 67,1 33,7 67,7 Stechenson. W. A. 8769 87.5 62.0 74.4 79 .6 76.1 Gri f fi th , P, E, 4401 94_4 R! P 7?_~ 91_7 a0_p f tiller. T. a - ca91 91.7 76.'70.0 32.7 30.2

/ /

Fields, D. A. 9042 91.1 79_ 74 ' og_o 94.0

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EXAMINATION RESULTS EXAMINER'S INITIALS P = Passed Only wutes of enamener F = Faded who actually admenestored W = Wavved the exarnmaton

r UNITED STATES j#p sey 'o NUCLEAR REGULATORY COMMISSION

-.. O ~,$ REslON 18 j j 101 MARIETTA STREET, N.W. -

ATLANTA, GEORGI A 30323 /

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%,*****/ .

,. ,. . ENCLOSURE 3 i

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- .e. 9 U. S.' NUC1. EAR REGULATORY COMISSION ,

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i-SENIOR REACTOR OPERATOR LICENSE EXAMINATION ;

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Facility: Crystal River Unit 3

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s Reactor Type: B & W 177 "

Date Administered: November 21, 1985 #

Examiner: D. Falconer i~l

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Candidate: ,

INSTRUCTIONS TO CANDIDATE:

Use separate paper for answers. Write answers on one side only. Staple question sheet on top of the artswers sheets. Points .for. each question. are indicated in - -

parenthesis after the question. . The passing grade requires at-least 701 in each cat and a final grade of at least 801.. Examination papers will be picked up .a four - hours after the examination starts. M i

Category % % .

Value Total Score Yalue Category -

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gI 5. Theory of Nuclear Power Plant.0-Operation, Fluids 'and Thennedynamics : , ,

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)NI g 6. Plant Systems: Design, Control &

Instrumentation gj 2[ 7. Procedures-Nonnal, Abnormal, Emergency Radiological Control M.II ,.

8. Administrative Procedures.

Conditions and Limitations kf . .. .. . .

TOTALS Final Grade- %

All work done on this exam is.my own, I have neither given or received aid. t .

Applicant Signature

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o i e s CATEGORY 5 - TMDRY OF 34UC1. EAR 30WER PLANT:0PERATION, FLUIDS AND d # ~'

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7 THERMODYNAMICS' m? - '~d .

(25.0) 5.01 . -; Indicate how natural circulation will be affected by each of the following situations. Consider each one separately and answer INCREASE, DECREASE, or NO EFFECT. . .

a. Reduction of turbine bypass valve. setpoint -

4 (0.5) u w

b. Decrease in OTSG level (0.5)

c. Reduction of feedwater temperature (0.5)

d. Increase in RC5 pressure (0.5) 5.02 An ECP is calculated for a reactor startup four hours after a reactor trip from 100% equilibrium conditions. -

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For each of.the following situations, indicate if the actual cri.ttcal rod position would be HIGHER, LOWER'or ' . .

NO CHANGE:.from the calculated critical rod po'sition. . . :/ -

Consider each situation separately and assume no other .

changes.J.-

a. The startup is delayed until eight hours after the trip. (0.5)

b. The actual boron concentration is 50 ppm lower than that used to calculate the ECP. (0.5)

c. Tavg is 535'F as compared to the value of 532*F .

used in the calculation. . (0.5)

c. OTSG level is stable at 40 inches on the startup. range. (0.5) 5.03 Why snoulc-RC cooldown on natural circulatic'n not exceed 10 F/hr for. Tc >280*F1 (1.0) 5.04 Assume that the reactor 1s at 100% power, beginning - -

of life, with Group 7 rods 90% withdrawn. Indicate -

if Group 7 must be INSEATED'or VITHORAWN to maintain the reactor at .100% power for the following evolutions. ..

(See APSAR Worth Curve, I';; ; 1.13, attached).

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a. the insertion of Group 8 from 36% to 15%. (0.5)

b. the withdrawal of Group 8 from 50% to 80% (0.5)

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, ,5.05 .. Indicate if.either DNBR;.or Pressure Boundary protection ,, i ,

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1,areuprovided by. the following Reactor Protection System -

Trips..,

.a

a. RCS Pressure-High (0.5)

b. RCS Pressure-Low : (0.5); 1 -

c. Reactor Coolant Pump Power Monitors (0.5)

d. Nuclear Overpower Based on RCS Flow and Axial Power Imbalance (0.5) 5.06 Indicate if the severity of the following accidents- ~

INCREASE or DECREASE wtth a positive moderator temperature-coefftetent.

a. Rod Ejection Accident- -

(0.5) 8

b. Steam Line Break (0.5) .

c. Loss.of Feedwater -

(0.5) - .

d. Rod Withdrawal Accident (0.5) 5.07 Tcold and Group 7 insertion affect the excore power range calibration. Indicate if reactor power det. ermined by the excore detectors will be LESS CONSERVATIVE or MORE CONSERVATIVE with the following conditions.

a. increasing Tcold (0.5)

D. inserting Group.7 (0.5) 5.08 Which one of the following factors'will help.. rather'than ( 1. 0 ) .'

[MC] hinder, natural. circulation?.

> a. Lowering OTSG 1evel N

.g b. Lowering RCS' pressure

.. d c. Increasing RCS temperature Lowering-turbine bypass valve setpoint

1. d. .

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5.09 . Answer 4ttte following statements concerning core power . .v f a ,

. distribution and therwal design limits, TRUE or FALSE. t v a7 e' a:;- Hot Channel Factors (F and g

FAH) are only monitored once far each new core prtor to exceeding 75% Full Power. (0.5) ..

b. The Quadrant Power-Tilt Limitr are more restrtetive .

when measured by Power Range Channels than by the Symmetrical Incore Detector System. (0.5)

c. Power distributton limfts are based on maintaining minimum DNBR, peak linear power density and LOCA.

analyses criteria. (0.5) 5.10 Which of the-following would tend.to. place the ICS closer >

[MC] to a BTU limit?. (1.0) .+

a. A decrease.in-feedwater flow.

b. An increase in feedwater temperature. -

c. An increase in OTSG pressure.

d. An increase in T,y,.

5.11 TRUE or FALSE Departure from Nucleate Boiling (DNB) D e . . " ' < . - :s following a LOCA. (2.0) 5.16 If the equilibrium count rate in a subcritical reactor

[MC] TRIPLES due to a reactivity change, what happens to the margin to criticality? (1.0)

a. decreases by 1/3
b. decreases by 2/3 -
c. decreases by 3/4-
d. reactor reaches a supercritical condition 5.17 The following data was obtained during a core refueling.
[MC]
Number of Asseabif es Loaded., . Neutron Count Rate - - -
0 40 cps 5 70 cps 10 90 cps
-. 15 - 115 cps.
Select the number of assemblies it will take to reach the minimum critical size. Use the attached graph paper if desired. (Assume equal assembly worth) ( 1.0)
a. 29 assemblies
b. 23 assemblies
c. 28 assemblies
d. 33 assemblies
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5.18- .r.Whicletaf..the followint would.cause the differential rodi e ,- < -*
wortle.torincrease? +( Assume. the rodzin questtort remains irt * - * ^
[MC] .
' the same-position and treat each parameter change n , independently) (1.0) l
' ,' a . -Arradjacent: rod is inserted to:the same height. - ' -
b. Moderator temperature 11 decreased 4. . .. . t. 5 > 4
c. Baron concentration is increased
d. An adjacent burnable poison rod depletes END OF~ CATEGORY 5' a.
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CATEGORY 6B PLAllT4 SYSTEM DESIGNJ CONTROL AND INSTRUMENTATIUK- ( 25.0)" .
S F.
i 6.01 List- two'af the mandatory slow zones for. the Main Fuel Hoist and the conditions for which they are imposed. (2.0) 6.02.. < What~ four conditions'( tnterlocks - not administrattve) must _
be satisfied to move the Main Fuel Handling Bridge on the- >
e &
n trolley? -
(2.0) s .. >
6.01. Transfer switches are used to transfer control from the control room to the Remote Shutdown Panel. List the location of each of these four switenes. (1.0) 6.04 Which of the -following is NOT a Main Feedwater Pump Trip. (L.0)
[MC]
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a. Low enheest hood temperature
b. Low lube oil pressure -
c. Loss.of governor speed signal -' -
d. Both.feedwater boostar pumps tripped
6.05 List the automatte actions that occur on a high radiation signal as detected by RMA-11 (waste gas decay tanks discharge to the auxiliary building ventilation system monitor). (1.0) 6.06 Answer the following with respect to the newly installed EFW. flow control values; EFV-55, 56, 57, 58. .
a. Mode of valve operation ( AC, DC, air, or other) -
(0.5)
b. Failure mode (open, closed . As. Is) (0.5)'
c. Means for local or manual control (if any). (0.5) 6.07 What is (are).the interlock (s) that ensure condenser- -
vacuus~ 15 broken before. the EFW pump suction can be 1 shifted from.the CST to the hotwell? (1.0) 6.08 The reactor coolant pump motor may be started three
. (3) times successively, from ambient toeperature or twice . -
from rated motor temperature. Additional repetitive .
starts are governed by motor operating temperature.
In the absence of thermal devices to determine both rotor and stator temperatures, what are the guideltnes for repetitive starts? (1.0) 1 1
7 Maximusaflow,for the DH pumps ts 4000 gpm. Minimum 1 6.09 e -
- 2 s flow is 80 gpe. Wnat is the maximum time tnat the '-
OH pump can be allowed to operate continuously in the.recirculati,on mode (80 gpa - 100 gas). (0.5) 6.10 - ' New ES MCC's have recently been installed at Crystal. .
River; MCC 3A3 and MCC 383. State the location of each f -
of these MCC's. Include Aux Bldg elevation and . .
1 "
+ '
reference a nearby piece of equipment or structure. : (1.0) 6.11 The turbine bypass valve / atmospheric dump valves may be biased by a O psig, a 50 osig or a 125 osig signal. Indicate.which of-these cias' apply to eacn of the four situations below..
1. The reactor and turtrine are not trtyped,- the turbine bypass valves are closed, and header pressure deviation .
is less than.10 psig. (0.5) '. . f'
2. The reactor is tripped as indicated by a TRIP CONF' light - - - i on the Diamond. Panel. ( 0. 5 ) ..- .
3. The reactor and turbine are not tripped, and ULD is. * >- '
U .-
greater than 15%. ( 0. 5) ~ - -
4. The reactor and turbine are not tripped, and ULO is less than 15%. (0.5) 6.12 The Unit is at 70% load with the ATc Controller in Manual (hand). One RCP trips. Answer the following,
a. Will the Unit run back? Why or why not? (1.0)
b. Will feedwater reratio? Why or why not? (1.0)'
6.13 MAR 82-05-01-01.has replaced _the.oristing RB spray actuation circuitry with a new systee..
a. List the two sets of conditions, either of which will a result in an RB spray PERMIT. (1.0)
b. In addition to.the R8 Soray PERMIT, what other signal is -
. t required for an RB Spray ACTUATION? (0.5) -
. c. The RB Spray PERMIT, once set, can be reset in anyone of tnree different ways. List eacn of these tnree ways. (1.5)
! r
8 r,1 - 1.14 .~ MARu77.-07-OL-11 resulted:.in changes in the Turbine Bypass e s IM Valve and Atmospheric Oump Controls. A 't
. .s a. :n The existing -10 to +10 VDC control scheme for the
,3 - . TBV's was changed to a 4 to 20 milliamp DC scheme.
What was the purpose of this modification? (1.0)
b. Explain.the ICS interlock (s) between the TBV's/ADV's .- .. . A .
a and loss of' condenser vacuum. (1.0) 6.15 The EFIC~ system will automatically initiate EFW upon detection-of various abnormal condttions. For each of the following-situations explain the reason or interlock that should prevent EFW from automatically initiating.
a. Reactor power is 105 and the only operating feedwater - -
pump trips. (0.5) t
b. Power level is 100% and the signal from OTSG; ' A' " Low - ,
Range" level fails to 0. (0,5) .
@ r During plant heatup (RC Temp. - 450*F), the three: operating: ".S.."
RCP's trip. (Gre-
+ J .
d. At full power an I&C technician causes an HPI actuation of ESAS Channel A only. (0.5) 6.16 Answer the following concerning the Safety Parameter Display System (SPDS). See Figures 3 and 5 attached.
a. Which NI, or combination of NI channels, provide the indication for "% PWR"? (0.5)'
b. Which incore, or combination of incores, provide the indication wnen "Incore Temperature".is selected?.
(0.5)' -
c. Following a reactor. trip the Reactivity Alert feature .
of the SPDS actuates. What does this indicate? (0.5)
d. What is automatically displayed on the SPOS whenever a - -
reactor crtp occurs (f.e., how does the SPDS respond to .
a trip)? (0.5)
.. END OF CATEGORY. 6 t 1 1
9 CATEGORY,- 7 PROCEDURES.s .MCRMAL ABNORMAL, EMERGENCY AND RADIGLOGICAL'- i d .We ~
CONTROL .
., .. (25.0) 7.01 AccordtNg to FP-203, what are the only two highly radioactive components that are allowed to be temporarily stored above the seal plate during fuel or core internals handling operations. (1.0) . ,
7.02 According to. 0P-404, how do you assure that..the DH . system will - '
.. s a w not tsolate on a spurious 284 psig signal during periods when- -
the reactor vessel head is removed. Include physical and administrative controls. (2.0) 7.C2 According to FP-302, what three enecks must be made by a fire brigade member prtar to removing the new fuel pit missle shield blocks. (1.5)
-7.04 FP-601 gives instructions on the rotation of fuel- assemblies -
'.i Miri gf g within the spent fuel pool. How is a 90* clockwise rotation accomplisned. (1.0) -
7.05 An actual: plume release has occurred.with a projected dose s'- .. . 'e to the general population of 15 Ree wnole body and 100 Rom -/- .' ' v- c
thyroid. If the wind direction is constant- from SSE to- NNW, answer the following for the general population. (Protective Action Guidelines Table 7.051, Evacuation Time Estimate Table 7.052, and Wind Direction Data Table 7.053 are attached.)
a. Between 0 and five (5) miles, which sectors should (0,5) evacuate.
b. Between five (5) and ten (10) miles, which sectors should
evacuate. (0.5)
(0.5)
c. Beyond ten (10) siles, which sectors should evacuate. . '
d. How long.will it take to evacuate handicapped.. elderly. ~ >
and hospitalized
individuals f rom within five (5) miles considering that. normal conditions.are present. (0.5) *
+
t
' I
10 7.06 .a. List the .Immediate Actions that are common (4dentica1) < 4 *- 4 .>
. f ar the four. Runback APs: 4 e * , v e V 3.
t loss'of. Booster Pump AP-540
., Loss of Main Feed Pump; AP-541 Asymmetric Rod AP-542 Loss of One RCF AP-543 '
(1.0) ' =
b. List- the additional Immediate Actions for AP-541 " Lass of Main Feed Pump Runback." (1.0)
c. Match the runback condition with the approximate power level at which you expect the plant to stabilize. (1.0)
~
1 Booster Pump a. 75%.
11 Main Feed Pump b. 70% .
iii Asymmetric Rod .
c. 60% P.
iv One RCP d. 55%
e. 50%
. 7.07 Fill in- the following blanks with regard to containment:'t.4C* ';-
access during Mode 1 operation.
a. Prior to any containment entry, personnel must (0.5) obtain a ( Form) and have it signed by (Title) .
b. Crew size will be a minimum of (number) (0.5) personnel and the maximum time in the containment building will be limited to (time) .
c. In the event that there are any personnel in- .
(0.5) -
the containment building- and the reactar- trips (action to be taken) .
7.08 The first Immediate Action of AP-380, " Engineered Safeguards. . ..
System Actuation," is to:
1.
Verify valid actuationt :
RC pressure <1500 psig or 3 ManuaT actuation .
,. What. are the> RemeditJ Actions associated with this step?' ( 1.5 ) -
7.09 Engineered Safeguards has actuated due to low RC pressure,
a. When are you required to stop the Reactor Coolant Pumps? ( 1.0)
b. Under what conditions (according to the Remedial Actions of AP-380) should the RCPs be kept running? (1.0)
El -
11 7'.10 " . OP '20$;; Power Operation, Section 2.0 states that "The expected 1 5 .;^
= various parametric system responses for reactor coolant:(RC) *
and steam supply systems are given below. Also included are
' allowable deviations." Assuming that the reactor is at 50
'4 percent power, what are the expected responses and allowable deviations for the following parameters? ,
a. RC pressure ( . 25 ) *
b. RC temperature (average) (.25)
c. RC temperature (inlet) (.25)
d. RC temperature (outlet) ( 25)
e. OTSG Outlet Pressure (.25)
f. OTSG Outlet. Steam Temperature (.25)
~
7.11' FilT in the following as stated irr OP-401, Core Floodirig-System.
a. CFV-5 and CFV-6 must.be- and .their breakers ".3 in the position; treater when reactor coolant (RC) is greater than 750 psig. ~(.75)
. b. CFV-5-and CFV-6 must be and their breakers in - ' . ' '
the position wnen RC pressure is less than- .- " .-
625 psig. (0.5)~
c. Core Flood Tank (CFT), temperature must be above *F before pressurizing the tanks. (.25) 7.12 TRUE or FALSE: An cperator must be stationed at RCV-5 (pressurizer vent valve) to accomplish venting the pressurizer in accordance.with OP 202, Plant.Heatup. (0.5) 7.13 The Immediate. Actions of AP-460," Steam Generator Isolation Actuation" call for the operator to ensure valves on affected-OTSG(s) are closed and selected closed. Assume a steam;line -
i break on OTSG 'A'. List:these required valves by name or number. (2.0)' -
7.14 An Immedtate Action of AP-555, " Continuous Contro'4 Rod - -
Withdrawal" is the.following: -
3. Stop red withdrawal:
a. Transfer rod (s) to alternate power supply.
5
a. Assume the af fected. rod (s) are in Group.7. List the- u steps required to transfer the rod (s) to an alternate -'
power supply. (2.0)
b. What are the Remedial Actions associated with Immediate Action (3) above? ( 1.0) 1 I
l 12 l
7 . 1 57.- 4 ICS. procedure 0P-501 states-in part, "If operating signal *
.e J s 7
[MC) source malfunctions make signal source transfer necessary. - ', / 7 *.
. t transfer to another signal source should be cone..."Which'one
, of thei.following CORRECTLY completes this statement? Assume
,the ICS has not responded to the malfunctioning. signal. (1.0)
a. immediately af ter placing the affected ICS statton -in - -
.r + . 4 HAND.
b. imedtately, regardless of ICS~ operating mode.
c. only after checking the computer for a valid alternate .
signal and placing the af fected ICS station in HANO.
, d. only after checking the computer .for a valid alternata signal; affected ICS station may be-in HANO or AUTO. .
END OF CATEGORY 7 m
13 CATEGORY 8.:- ADMINISTRATIVE PROCEDURES, CONDITIONS AND LIMITATIONS ,
( 25. 0}' ** .*
8.01 I '.The operational' action limit placed on OTSG leakage -
-[MC] is set.such that there exists up'to one week until ,
the tube ruptures. Whicn of the following leak rates corresponds to that operational limit. ( 1.0) 3.0 gpa f a. -
b. 1.0 gpm
c. 0.3 gpm
d. .03 gpm 8.02 While performing a valve lineup verification, a -
valve is discovered with a red tag in other than-the required position. Should the verifier sign-off -- .
this valve with a note indicating that the valve position.is controlled.by.a red tag?. Explain'your .*
answer. (1.0) 8.03 What two conditions ~ must be satisfied to.use the . . *' - -
PORV (RCV-10) manually to avoid high pressure reactor ;
trips during emergency conditions? . ( 2. 0).; C- -
8.04 Can the designated " Operator at the Controls," in the event of an emergency af fecting the safety of operations, momentarily assist an ISC technicians at the rear of the control room ICS panel if his actions are directiy related to the emergency? Explain your answer. (1.0) 8.05 State the requirements for correcting an error in a shift -
log book. (1.0)
. 8.06 TRUE or FALSE:
a. Ocen annuncia tor links are recorced in the Equipment- (0.5)
. Out-of-Servit.e Log
b. ES systems which are logged in the Equipment Out-of- (0.5) '
- Service do not require independent verification of proper.
. alignment-per CP 115,.In-Plant Clearance and Switching -
Orders, before returning the equipment to service.
, c. The Shift Supervisor can recuest e SOTA to escort an (0.5)
1. NRC inspector to Unit 5 so long a: the SOTA can respond to the control room within 15 minutes.
d. In the interim between reactor trip and approval for (0.5) recovery, the Nuclear Shift Supervisor may authorize withdrawal of Safety Groups 1-4 provided a 1% delta K/K shutdown margin is maintained and rod withdrawal is not prohibited by any RPS " Action Statements" of Standard.
Technical Specifications.
~
I I
. o 14 8.07 * ~After using2 the PORV to prevent a reactor trir from 100 -
i a .5..
2. percent power.on RCS pressure - high, indications lead you :- P 5-
- to suspect that the automatic reset of the PORV is out of -
calibration at 0200 hours0.00231 days 0.0556 hours 3.306878e-4 weeks 7.61e-5 months . You. request a calibration of the- -
. PORV lift setpoint and reset setcoints to verify PORV operability. The calibration procedure requires removing -
power to the PORV's solenoid valve which occurs at 0230 hours0.00266 days 0.0639 hours 3.80291e-4 weeks 8.7515e-5 months 9 -
Answer the following.for this situation. (Technical .
.+. z e Specifications are attached)r
a. By what clock time must the block valve be closed to (1.0) avoid being in Hot Standby witnin 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months ? Explain your decision.
b; Attempts to close -the block valve at 0245.hourt are : (1.0) unsuccessful _ '. I&C ' technicians deteretne that the pressure a bistable must be replaced.wbich may take up to 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months . c Since the PORV is already closed and power removed from - -
the solenoid, can operation in Mode 1 continue? Explain. .
4
. While in Hot Standby, the pressure bistable is replaced <, t ( 1.0)' -
thus returning the .PORV to operability; however. .the block. .+ .- .-
valve remains inoperable in the open position. Can the - -
unit return to power operattons? Explain your answer.
8.08 DG 'A' which supplies ES 4KV Bus 'A' is Inoperable. LPI (1.0)
[MC] pump 'A' supplied by ES 4KV Bus 'A' is inoperable. The Teco Spec for ECCS subsystems and AC sources are attached. Which statement is CORRECT concerning continued operation in Mode 17 (Technical Specifications are attached).
a. The Action Statements for both the.LPI pump and the DG are applied independently, each must te restored to .
OPERABLE in 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months ,
b. Since the OG-is required in Mode 4 and tne LPI pump is not, the Unit must be taken to Moce 4 witnin;72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months .
c. TS 3.0.3 applies; .it requires action to place the unit -
1 in a'moce-in wht:b the specification.does not apply , e" within I hour.
s d. TS 3.0.5 applies; it requires action to place the unit
. in a mode in which the specification does not'acply -
within 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months .
' f ~
L ! I
15 8.09 - t. in' ther event that. overtime must be used, the following omrtime ? ., x .9
. ... resteictions should be followed: -
e *
.a. YA n individual should not be permitted to work more (0.5) than . hours straight (not including shift-turnover stine). .
b. There should be a break of at least- hours . ;
(S.5)v e .
(which can include shift turnover time) between all work pertods.
c. An indivicual should not work more than 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months (0.5) in a . day period.
.d. An individual should not be required.ta work more than- ( O'. 5) consecutive days without having two consecutive cays off. >
8.10 Answer the following concerning the Emergency Oose Assessment ,
.a s' -
System. .
a. What is the purpose of the Emergency. Dose Assessmenty v.%(1.0)er .O - .
Assessment system?
b. What two functions of the Emergency Dose Assessment (1.0) system may operators be called upon to use?
8.11 What are the three (3) categories of decisions that the (1.5)
Emergency Coordinator can not delegate the responsibility for?
8.12 While in Moce 1. At 0500 hours0.00579 days 0.139 hours 8.267196e-4 weeks 1.9025e-4 months , contract construction workers (1.0) sever the power supply cables to the motor driven emergency
feecwater pump. At 0800 hours0.00926 days 0.222 hours 0.00132 weeks 3.044e-4 months , the turbine driven feedwater pumo is rendered. inoperable. If these events occurred on June 3,1985, .on what date.and at what time must the unit be in Hot Standoy.should repair efforts not be. completed on both pumps? (Constder Tech Spec reoutrements only).
(Technical Specifications are attached). -
. 8.13 With one pressurizer code safety-9alve inoperable and the (1.0) -
plant in Hot Standby, can the plant be taken to 4 percent power? .
E: Explain your answer. (Technical Specifications are attached).
l
' t i L
16 8.14 .. Technical Specificattons.on RCS Outlet Temperature - High .- (1.0) r- 3:
[MC] . reactor protection system instrumentation requires a monthly 2 r channel functional test. This test wa:: performed at-tne -
following times:
~
1. October.15 at 0400
2. November 19 at 0400 * . 2 .c .
3. December 24 at 0400 . . , .
Which of the following is the latest date that-this test can-be performed without declaring the instrument inoperable?
(Technical Specifications are attached).
a. January 20th
b. . January 23rd
c. . January 26th.
d. January 31st:
8.15 Match the.RCS' leakage. types in Column A to the Technical .
(1.0) . -
Specification limits in Column B (assume plant is in Mode 1). > ... ..<. -
(Technical Specifications are attached).
Column A Column B
a. PORV seat leakage 1. O gpm
b. OTSG tube leakage 2. I gpm
c. Leakage from unknown location 3. 5 gpm
d. Leakage from weld crack on 4 10 gpm the pressurizer surge line 5. 6 pgh 8.16 Consider the table concerning RCS leakage past CFV-1 during a -
reactor startuo' and answer the cuestions below. (Technical -
Specifications are attached).
Time ,
power CP/-1 Leakage 0100 hours0.00116 days 0.0278 hours 1.653439e-4 weeks 3.805e-5 months 15% 0 gper 0600 hours0.00694 days 0.167 hours 9.920635e-4 weeks 2.283e-4 months . 50% 2 gpm 1800 hours0.0208 days 0.5 hours 0.00298 weeks 6.849e-4 months . . 80% No Measurement Made . - -
2300' hours 100% 4 gpm
a. Do the Technical Specifications allow the unit to be (1.0) at 80 percent power at 1800 hours0.0208 days 0.5 hours 0.00298 weeks 6.849e-4 months ?. Explain your answer.
b. During shift turnover, at 2400 hours0.0278 days 0.667 hours 0.00397 weeks 9.132e-4 months , you are handed the (1.0) 4 gpm leakrate measurement. What actions are required by the Technical Specifications?
8.17 Fill in the blanks. Each containment air lock shall be (l.C)-
demonstrated operable within ^ hours after a single (o ,% .
gfi hours after multiple pg entry and at least once per entries. -(Technical Specifications are attached).
4A
l 17 8.18 ~ 2 ' ' 'The' reactor? coolant: average temperature was reduced to below (0.5) e d
- - 140*F-with a reactivity condition of less than .95 Kef f in
- ~
+ preparation for personnel to make the initial containment -
. entry to prepare for refueling. What mode is the plant in?
(Technical Specifications are attached).
s, 4. t 4
o, - * ~ e END OF CATEGORY 8 j ,. . , , ,
e r.
9 e<*
.. s.
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l h "I = ag -
(density)
..________1(velocity)1(ares)1 = (#nsity)2(velocity)2(aree)2 '
' e ..
i KE = mv2 PE = agh- PEl +ME191V1 = PEZ+RE24 2VZ -
.. T, where'V-=esII*umeific v P = Pressure
=-
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9
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et ta .K . = (K,ff.11/K,f f cal (1.u fft) = ca2(1-Keff2)
. ?. r-M = (1-K,ff1) son - (1-Keff) x 100s ;
. . . . ,(1-K, g,
...__..................f.f.......................................
. . . . .f.f.j )
decay constant = In (2) = 0.693 A = A,,-(decay constant)x(t) t 1/2 t1/2 Water Parameters- Miscellaneous Conversions . .. .
1 gallen = 8.345 lbs: 1 Curie = 3.7 x 1010 dys: . . -
1 gallon = 3.78 liters 1 kg = 2.21.lbs .
I ft3 = 7.48 gallons '. . I hp.= 2.54 a 103 8ts/tr. .
Density = 62.4 lbm/ft3 . 1 phe = 3.41 x 106 Bts/hr . v .
Density ek p/cm3r ~
1 inch = 2.54 centimeters - ' ..'
Heat of Vaporization = 970 Stu/lbe Degrees F = (1.8) x (Degrees C);+ 32.
. Heat of Fusion = 144 Stu/lba 1 Stu = 778 ft-lbf 1 Ata =-14.7. psia = 29.9 in Hg g = 32.174 ft-ibs/lbf.sec2
. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . _ _ _ _ . . _ _ . . _ _ . . . . _ _ . - - ~
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.r APSR Integral Reactivity Worth 0% FP, CBC.1-7.at 100% wd, No Isaan ~
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OP-103 Rev. Page 53 i :
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4; A
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CURVE SELECTION , PRIM ~ PRIM. PR6M ' . . : s ..
i tu E9BE a
act EEXE usar Jll gg g REDUN REDUN REDUN .
T<OLO T-HOT RCS-PRES
! FIGURE 3*
SPDS CONTROL. PANEL .. . .
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TABLE 7.051 GisIDELlegs FUt earmeew8n MIDTICTIVE ACTIOW PGl ausms PupIE Dr0SUIE*
.em-__ _ mee wrw < _ _ - ___ AIW - _ _ _ _ rwnATTaft 7 9&
g
,. cw .' -y...
eECOISEEDGED ACTION w wfffWe * ,
Two elle, 360', pressutionary everustion.
Five elle smelter of potentially offeated sesfors.**
1. A General georgency hee. teen deciered.
Two elle, 360*. C -- tienery eresuetles. . . , '
2. A General Energeacy hos been dealered. Five elle ovesuetion of potentially ettected moeters.**g .
Sutetential emm.desage la progress or projasted. . , j Me conteineemt fellere.tos test grejested. .
No estetential tission product levenvory in contetneart. ' __.
3. A Generei Energency hee IIeen desIered.
Substential core demoge in progrees or projected.
$AsIE AS M OTE IIe centelement tellure hos been projected..
FIssten product Inveni y la centel... _--t < GAS GM. -
Five elle, 360*, ovecuotles. . .
4. A Genere4 Boergemey hee been dessered.- - Tem enle eyeseettee et poteettelby ettouted sosters.** p.
SutetsofteI eere damage le progrees er gradested.-
Osntainment tellere med ro6eese 44temey not est lemeesses
Fleelee presset levestery la sentelement s edS er.
Five elle, 380*. evesdotten. . . .
5. A General goergoesy too.toen dem6ered. . Tem elle spesestles et petustielly ettested moeters.**.j. 1t i SubstentIei aero desage le progrees er arejented. Sheifer erees unicle een not to owesunted to6ero psumm Centeleenst fellere is projected to to lesinent.
predest leventury le esurtaineett.
No estatestiel'il arrivel. -
Qr
6. A Generel Georgency hoe mese.desiered. SasE AS'ASDUE
q Sutetentist oore damage la progrees. .
Containment tellure is projected to be feminent. *
Fission product Inventory in containment > GAS GAP.
An actual reisese has occurred or is in progress. Two alle, 360*, shelter. .
T. len elle shelter of potentially effected sectors. "
Oose to the pooulation is projected to bei e) mole Body >0.5 to 41.0 Ren n) Thyroldr >1.0 to 3 0 Ree Two alle, 360', evacuation. .
8. An actual reisese has occurred or is in progrees. Ten elle evacuation of potentially ef fected sectors.**
Deen to ttie peoulatlea is projected to to: Ten elle smelter et remaining sectors.
e) emele sedy >l.0 to <5.0 Ree .
b) Thyroles >S.Oto{25Ree ,'
Five elle, 384', ovesietles.
9 An eetwee rolesse hes secorred or is lie progress. . Ten elle evocation of potentially ettoeted sectors.** * ,
I Does to tMe pooulation is projected to hos Ten elle shelter of reseleing sosters. ; I .-
el mole tedys . >S.0 to < 29 men -- .
bl Thyroldr > 25 to 325 peo Centret esposero et sourTency- warmers, emeest per . ,
10. An actual ratesse too oceerred ar-lo in progrese.. liteneving missiamo to 25 Ree emele tedy,125 Ison "
)
Oose to the population is projected te not Thyrold. I Appropelete controls for energency workers -
el mole Body: > 25 to 4 75 Ree Include flee lleitettons and respirators.) .
Di T W dt- bl25 Ase . .
Castrol espesure of emergency verisors p LN ' 3 II. An acteel re4eene has emeerred er is la progrees. litseeeing missione to 75 Ree ehele gedy. 50estret et - !
l Does to the populettee Is. projested to ties time orposere elli be east ettestive.) IIDTE: Al tneuger-el mole Bodys , >~ 73 pas ~
respirators should to used where ettective to control does to energency veriners, tnyreld does say est to a lletting teater for liteneving steelene, f
' ' MOTE:
References for this feele are e camelneflon of Teele 5.1, page 3.31 Rev. a/73 . asenval of Protective A Nucteer incidents and MJREG-0654, dated I/SO.
8 and adjacent sectors.
, g 'Mfected sectors f aciude, as e einimus, the downwind sector (s)
Page 4 Id Osto 03/01/54 EM-203 Rev.
j l
I
-~ ---w -p---_ _ _ . _
TABLE 7.052 i ,
C -
EVACUATION TIME ESTIMATE TABLES
SECTORS
Ofstance A-D E-H J-M N-R All (miles) Hr.-Min. ..,, Hr.-Min, ,, . H r.-Mi n . ,,,Hr.-Min. _ , H r. -Mi n . , ,
GENERAL ~POPUL'ATION (NORMAL CONDITTONS) _ ,,, , , , , ,
0 - 2** 1 - 30 0 - 45' O - 45 0 2 ' ; 30 '
~
0 'S 1 - 30 1 - 30 0 - 45 **- 0 - 45** 4 - 00 0 - 10 3 - 00' 3 - 00 0 45** O - 45**' '
6 - 30 60%RAC POPULATTON TAUTER 50CIMITTON57 ' ... .. .
0 - 2** 3 - 00 1 - 00 1 - 00 1 - 00 4 00 - *. .. ; .*
O-5 3 - 00' 3-00 - 1 00**- l ' 00** * ' 8 - 00" ' - </*
0 - 10 6 - 00 6 - 00' 2 ' - 00**
2 - 00** '/ f. ?.13 2-: 00 i M . ' " ' .
SPECIAL POPULATION'(NORMAt. CONOTTIONS)***
i,7. '
"'^ "'^ "'^ "'^ "'^
O 0-5
- 2**
2 - 00 2 - 00 N/A 5 - 00 N/A 0 - 10 3 - 00 3 - 00 N/A N/A 6 - 30 SPECIAL POPULATION TADVERSE' CON 0!TIONS)***'" .
0 - 2**~ N/A N/A N/A' N/A- . M/A -
0-5 4 - 00 4. 00 N/A'. N/A' N/A. .
0 - 10 6 - 00 6 - 00 M/A' N/A'- 13 '- 00 : -
These are conservative estimates .and are inclustve of warning times. . t .
These estimates are for personne1' ort'FPC property.- Evecuatton time is based:en -
a staged / sequenced generating complex evacuation via the plant access road.
This category includes the handicapped, elderly, and hospitalized individuals and is inclusive of the general population.
O EM-203 Rev. 14 Date 03/01/84 Page 5 (LAST PAGE)
I f I
TABLE 7.053
+ 1 ,**
WIW DIRECTION ORTA -
, _ . Wind Fras ,_ ,,
Degrees'_- Wimi- Tensert ,_ Sectort Affected .,. ,, i N - 349-11. 5 HJK '
. . s e
'j
' ng ' 33 '
SSW JKL # - -
. g; 34.gg, . -
SW .- KLM- '-
2' N i 0;. EE 57-78 WSW LMN MNP E 79-101 W ESE 102-123 WW- MPQ h SE 124-146 W PQR
SSE 147-168. luti 0AA 5 169-191 A A 8-
' ,. N -
SSW - .- . 198 213 . - luEi 'A 8 C' !
' 5W -
214-23E. . K- - '
'8 C O e WSW -
237-258'. ~. EE -
C D E'
3 l W 259-28 L E D E F- -
"I FP' WW 282-303J ESE~. EF6' 2
\
. ' . d ~' '
llQ' : W 304-325.'- SE FGM - '
[R' neef 327-344 SSE GHJ .
/.>''
s e 4 ee e
I I
. _ . . -. __. - - - . . . _ _ .= _. - _.
I 3 . .
<- , g
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.s TABLE 1.1 -
.9* ft+ .* -t*-
. C;f'. . ' . - a*[' r1 '4.f.
~
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, . . - ;. . .=
. . .. .r.
REACTTVTTY 2 RATED " AVERAGE CDOUWT ,'
g -
CONDITION. K,g . THrigent powgme , TDFERATURE 'Cl.;( I'
1. PtBEK (FEMTIM > 0.2 > R.
L23E4
.- 2. STARTtr > 0. M . < > 250*r
,s
_ 51 3 .NOT ITAMsf .
0. M 0 > 200*F
4. NOT SWTUDist < 0.95 0 Iso *r's Tag > 200*F .',
5. COLD 3NUTDOW
< 0. 9F - 0' f,.2OOT '
RE M I. Ins ";) .. .
4. 0.95 14045 i'i . ' .4:
0 <
%p
. ~
Excluding decay beat.
Reactor vessel head uneolted.or reoved and fuel in the vessel. -
l l
L. .
CRYSTAL RIVER - UNIT 3 19 Acendment No. 69 f
! I
3/4 LIMITINE CON 0!TIONS FOR OPERATION AND SURVE!LLANCE REQUIREME _ _ , , , ,,
3/4.8 'APPLICA8!LITY '
i
]
.. LIMITIM CDm! TION FOR .WERATION '
~ '
3.0.1 Limiting Condttfaus- for Operetton and ACTTON requirements shali- -
he applicable during the OPEAATIORAL WE1 or other candittans spectfteds "
n Ve for anok spectftcattanc . -
3.0.2 Adherence" to- therreguiremener of-the- Lturttingr Canettior'fe Oper* -
ation and/or associated ACTION within the specif ted time interval snail
constitute comp 1tance with the spectfttatter. In the event-the Lf atting Conditten for Operetten-is restored priertta-ampiration of the specified g., tiae_internel, complettas af-the:ACT105 statammet ta met required.- .
3. O. 3 p4 P
1 in the associated ACTION requirements,. withts L hour ac
placiagaft,'ascapplicable, inrto place ths unit- in a MtIIE in which the .
1. At least' HOT STAWSY withfn the nest 5; hours " '
2.. At least MOT 5WTDOW within the fe11 swing 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months ; and9
3. At least CULD SWTDOW within the subsequent'24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .
Where corrective measures are completed that permit operation under the ACTION requirements, the ACTION may be taken in accordance with the specified time limits as measured from the time of failure to meet the Lief ting Condition for Operation. '
Spect f fcations. Exceptions to these requirements are stated in the 'ndividual 3.0.4 Entry into arWEIATIMAL MIE or ether sysetfted appffesktitty #
casetttes shall est he ande.eslees the asettttems at the,Lisettss Caso ettles fWr9peretter are met withest relianer en previstent contained.fa-the ACTIS statements anlace seterwise essestad.m This praetsten shett % ,
not prevent passage thw WERATEMAL #WE1as.regatred to tasyty with?
ACTim sememmamen_ ,- -
l 3.0.5 When a system, sidtsystas,; train, component or device' is deterwined ta. t ,
he inoperette sately.D=rmaam its seorgency power' source is inoperstleh er. c ;
safely because its'nenmal peuer source is inoperable, it may be considered : l., ?
OPEMBLE.for the purpesa of satisfying the requirements of its appitcable ^
t.tsiting Candition for Operation, provided:. (1) its corresponding normal er -
1
~~
emergency power- seurca.is OPEAAOLE;.and (2) all of its.redundantzsystas(s), j syksystem(s).- train (s), unsponent(s) and device (s) are OPERA 8LEJ er likewise 1 satisfy the requirements of this specification. Unless both conditions (1) !
and (2) are satisfied, within 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months action shall be initiated to place the '
unit in a MODE in which the applicable Limiting condition for operation does i not apply by placing it as applicable in: !
1. At least HOT STAN08Y within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months , #
2. At least HOT SHUT 00W within the fo11owing-6 hours, and:
3. At least COLD SHUT 00W within the subsequent 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .
This Specification is not applicable in MODES 5 or 6.
gCRYSTAL A!VEA - UNIT 3 3/46-1 Amendment No. 49 l l
APPLICMILITY . i SIRMILLANCE R@!RDUT5 ;-
r,,?. .
u, a,
? ?j 4.0.1 Serve 111ance Regnimeents shall be applicable during the WERA-1 -
TISIAL NMIES er other condittans specified fhr tnetytdual Ltetting Candittons fer-operetten usless etaerwtes etated to-an-indtofdual Sur. .
,. . vet 11ames Raguirement... .
4.0.2. Each Surveillance.Aeguirement shall be performed.udtkin the; & % * . u'
speciffed.tten interval with

-
, s. A maximum allowable extenstes not-ta encaed-2SE:of the arw weillance. interval, and.
b. A total meatmarcontrtnet-tntervel tierfer esqr 3 casessuttwe -
tests. net-tm.amcaed125 times the spectfied arve111ance -
1starvel.. .
l t
4.0.3 perftrmance'er a Seryw1114mse Requirement vfthis the specified . 'O l
time intervel.shall constttata compliance w6ter tpERASILITY regstrumenteN - . ',
for a Lietting 4l unless otherw s,Cendition e: required for Operaties ap"the and assestated specificaties survet11anca Actier statements.w:'.
angstoo- W C.'. '
I monts de met have.ta be perfarnet en taeparable. egatament.: *G '
2 i'
4.0.4 Entry inte arr CPUtATToltRL M10E er ether specified appiteattfifty - !
conditions shall not be made unless the Surveillance Requirement (s) as-sociated with the Lietting Condition for Operation has been perforand within the stated surveillance interval or as otherwise specified.
I
4.0.5 Surveillance Requirements for inservice inspection and testing of l ASE Code Class 1, 2, and 3 components shall be applicable as . fellows

1 i a. For the time period frem issoasco ef the fact 11ty Operating-- -
L1casse to-the start af. faciltty commercial .sparetteng inser.
! vice testing vf A510 Code Class 1, 2, .and 3' pumps and valves - -
{ shall he.perfereed in accertance with Sectiem 21 ef the AGIE.....-
i leflor ent Pressere tossel Code 4974 Editten; and Addende .-
l thresgk Summer.1975,. emcept imers: specific urtttaa relief; team i been yested.ty the Cammission.
. b. For the time parted following start af fact 11ty commertfal'ap=,- - -
eretter, inserette inspectteur er ASM Code Class 1, 2, and:3. !-
campenents and inservice testing of ASME Code Class 1, 2, and 2 3 pumps and valves shall be performed in accordance with sec-l tien XI of the ASE .Be11er and Pressure Vessel Code and app 11-cable Addenda as. rupstrud by 10 CFR W :Section 50.55s(g), est capt uhers spectfic written mitef has been Fanted by the i Commission pursuant to 10 CFR 50, Section 50.55a(g)(8)(1).
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) CRYSTAL RIVER - UNIT 3 3/4 0-1 Amendment fen.-40 1
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APPdCARILITY '
smWILUIICE E91RDOT5 (Continued) . ..
P erformance of the aheve fnservice inspection and testtng acttvitiesThe shall be in addittom te other spectfied survet11anca tenutrements.
prov 1s1ans of Spectfistatien 4.0.1 are not applicable ta surveillance ::
ntervals associated with taservice fespection and testtwg activittea- .
Pad i
required by Section E af tha ahama ASME Bailee anLPressure
~ c "
Vesse
' - and appitcable Addende..
e m
A*'nd'ent .fts . 40 CRYSTAL RI ER - UNIT 3 J/4 0-3
,i 4
I L_ ____
~
s atACTOR COOLANT SYSTEM _ ,
RELIEF TEVt3 - (PERATINE ,, , ,
C00t SAFETY VALVE 5 .., '
LIMITI E CONDITIUR fur (FEMATTot
- v, 3.4.3.T ATT pressurizer code safety- valves shall he OPERA 8(I with a e
Itft setting of 2500 psts + 1s.-
o APPLICASft,!TY:;, MOtKI'I, .2. andri .
AcTTOR:' .-
.?
Wtth one pressurirer. code safety valve inoperahle. either restere-jthe ,. . y .
inoperable velve to OPERABLE . status' within 15 minetes or to.;ter.W: ~ .
5WTDOWN within 12. hours. - '
SURVE!LLANCE REQUIREMENTS 4.4.3.1 No- additional 5'urveillance; Regetruments-~ ottier- thow 'those ,
required by Specification 4.0.5. -
CRYSTAL R!yER . ' UNIT 3 3/4 4-4 Amendment No. 38. 55
/
REACTOR COOLANT SYSTEM POWER OPERATED RELIEF VALVE 5
,. s. % '- . .. ;
(
LIMITINGWENTION POR OPERATION 4
3.4.3.2 The power operated reliet valve (PORV) and Las associated block valve shall be - !
OPERA &M.,.-
1 APPLICA5fLTTY: @ES b 2, and 3. ,
I ACTION: _ .
1
a. With the' PORY inoperable, within ! hour either restors the PORV to OPERABM status or close the associated block valve and remove power from the black walves otherwise, he in at least HOT STANDRY within the next 6 I
hours and in COLD SHUTDOWN within the fattowing 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months . -
b. With the block velve Inoperable, within I hear either restore the block vehse to. .! 4 OPERABLEr status er cisme the tieck valveeut remove power from the %' * ,
valve or ciosa the PORV and removem from the associated mennold valves 4;
q j
/'
(
otherwise, be irt at least HOT STAND 8Y w6 thin the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and.traCOLD'.it ' ~ i SHUTDOWN within the following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months . ~
i c. The provisiers of Specification 3.0.4 are not applicablev. - -
i SURVEILLANCE REQUIREMENTS .,
l 4.f. .).2.1 In addition to the requirements of Specifications 4.0.3, the PORY shall be !
demonstrated OPERABLE at least once per 18 months by performance of a CHANNEL CALIBRATION. l i
r l 4.4.3.2.2' !
The block valve shall be demonstrated OPERABLE ~at least once per 92 days by
, operating the valve through one complete cycle of full. travel '
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l CRYSTAL RIVER - UNIT 3 3/4 4-4a Amendments Nos. If, $$, 7),77 '
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1 REACTORCEAffSYSTEM OPERATIONAL LEA p4E LIMITING CCNSITICN FOR OPERATION . m- - - -
3.4.5.2- .Reacter Coolant System laakage shall be limitad tar. .
, . '4. No PRES 5URE louMDARY LEAEAGE, bc 1'GPM UNIDDITIFIED' LEAKAGE, . . .
4
c. 1 GPM tata.1 - primary-tn.amenm+ary leakage through-staarges.ai.t!.w . :*.- -
eratars.-
d. 10 GPM IDENTIFIED LEAKAGE,from the. Reactor.: Coolant System,
, e. 10 G;H CCNTROLLEU. LEAKAGE.at.a Reectsr Coalant- System pressure of 2150 '+ 20 pstg, and-
f. . t -
' j'.
Leakage Pressureas speciff Valves Isolation ed in Table.3.4 identifled 2 for
-in these Table.p.4 gr Coolant Systom- -
APPLICAltLITY: 700!S.1, 2,.3.'arns:4 .
ACT!0N:
a. Wi n any PRE 55URE'30UN044Y LEAUGE,' be in at least NOT STANO3Y ~
witnin 6 hcurs and in COLD SHUT 00WN witn c the following 30 hCurs.
b. With any Reactor C;olant System leakage ; eater than any one of the above limits, excluding PRESSURE SCUNDARY LEAXAGE, .
reduce-thesleakage rate to.within limits within-4. hours or be '
'n at- f east HCT STANDEY within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in COLO ~
SHuTD0h4 wiutta tha.follem6ag.30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .'
c. With any MCoolant.Systser Pressure : Isolation Valve leekage pater? '
tnan the acove J4srf ti rwector .sperattun may . continue pnnrided:that at -
least two valveskirr,eech hir'r pressure line-having a stan. functional;. valve- .
are in, and remain *ing the mode correscondtng to the isolated conditten. ' l
(.ttor operated velves shall be placed in the closed po11tton and power *. '
supplies egenergized.-)a .
d. The provisions of Section 1.7.4 are not acetic:: ele for entry into .TCES 3 T and 4 for the purpose.cf .testtng the isolatton enact valves.. -
CRYSTAL RIVER . UNIT 3 3/4 4 15 crear ord.4/tu/ul l 5
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REACTOR C00LAt;T SYSTEM SURVEILLANCE REQUIREMENTS 4.'4.6'2.1" Reector Coolant System leakeges shall be demonstrated to tw within each of the ancve 1imits by:
a. Monitoring the cantatteent atmosphere iodine radioactivity monitor at least.cnce per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months , -
b. Monitorinir the c: taiteen; st..Minventury and discharge at -
least once per 12 nours,
c. Measurement cf the C0riTROLLED. LEAKAGE from the reactor coolant.
pumsr seals when the Reactor Coolant System pressure is
. 2150 1 20 pitg at least..cnce per 31 days,
d. Perfannonce of a Reector Caolant Systaw weter inventory balance -
J' at least once.per 72 Pours during steady state' operation.- N 4.4.6.2.2. Each Reactor Coolant System Pressure Isolation Valve specified(in ..' .
Table 3.4-2 M000 2.by shall be indivtdually verifying leakage demonstrated OPERA to be within its limit: 8LE prior ta ' entering' -#"* J; ,' -
a. After eacn refueling outage,
.b. Whenever the clint has been in COLD SHUTD0m for 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months , or more, if leakage testing has not been performed in tne previous 9 nonths, and
c. Prior to retur' ning the valve to service following maintenanca,
repair or replacement work on'the valve. '
4.4.6.2.3 Whenever integrity of a pressure isolation valve listed in Table-3.4 2 cannot be demonstrated, the integrity of the remaining valve in eactt-higM pressore line having a leaking va' We shal1~ be detemined and recorded * -
. daily. In addition, the position of the other closed valve located in tne -
high pressure. p1ptng sna11 be recorded daily.
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i 3/4 4 16 nd CP.YSTAL RIVER - Utilt 3 drd . )2 81 1 1
. . TA8LE 3.4 2 REACTOR CCOLN47 SYSTEM PRESSURE ISOLATION VALVES Sys ten- Valve Maximm Allowable Leakagef a)(b)(c)
-' L: ;0ecay Heat / Low C/V-1 < 5.0 gym
Pressure. Injection -
OHV-2 < 5.0 gem CFV-3 < 5.0 sps. ' - -
CHV-1 < 5.0 gam-O Notes :
(a) 4 mimum A11amable Leakage (each valve): ,
r
1. Leakage rates'.less than or equallto.l.0 gem are consteered acceptable.;O
2. Leakage rates greater than 1.0 gprrbut less then or eque12tof 5?D5,put 'N are constcerad acceptable if the latest measured. rete.het.nor:enceeded.1 the rate deter atned by the previous test.ny an amount that. reduces.tnew margin between measured leakage rate and :ne maximum permtssible rate -
of 5.0 gpm by 50". or greater.
3. Leakage rates greater than 1.0 gpm but less than or equal to 5.0 gpm are considered unacceptable if the latest measured rate exceeded the rate detemined by the previous test.by an amount that reduces tne '.
marptn between measured leakage rate and the maxtrun gemissible rete' of ..] gpm by 50*. or greater.
4 Leakage. rates greater than 5.0 gem are considered unacceptable.t.
(b) To s a tis f/ ALARA ' requirements , lea.kage. cay be reasured indtractly las :
from tne perferrence of pressure indica *. ors) t f accomplished in accordance with accreved procedures and succorted by corvutations snowing tnat the metnod is capable of demonstrating valve complianca with tne leakage:i . .
criterta.
(c) Mtntetn differentist test pressure shall not be less than 150 pstd. .
CRYSTAL RIVER V'ilT 3 3/4 a 184 Order dtd.4/20/81 l
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l-DERGEMCY CORE C0OLING SYSTEMS
.; e i
m SutSYSTEMS a T. L., , 280*F , <
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! .... . - . .. LIMITING CON 0! TION Ft)K OPERATTON
~- - 't ~ .
3.5.2 Two independent ECCS subsystems shall ha GPEERSLE with..eech, . , , , i, o
3 subsystem comprised of:-
a. One OPERAELE high pressure infectieur(r!) puser,:
b. One OPERABLE low ' pressure injectierr (LPI) pop,
c. One CPUIASLE decay heat cooler; and: . .
d. An OPUtAKE:fitw~ path capable of taking'section from the j borated untar storege tank (W5T) .en a safety injection signal .~.4 and manually transferring suction to.ths.costalammet sump;euring pi the recirculation phase of operetten. -
.r .. . .,
APPLICA8fLITY: MODES. I . 2 and 3. . , , .T * ,
ACTION: .
a. With one ECCS subsystem (noperable, restore the inoperable subsystem to OPCAA8LE status within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months or be in HOT SHUTOOWN within the next 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .
b. In the event the ECCS is actuated and injects water into the ,
Reactor Coolant-Systems a Special Report shell be propered one suturitted to the Commission pursuant.to Specification 8.9.2 ,
withinW days describing the cirtumstances of the actuation c-and the total accumalated actuation cycles to date. -
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CAYSTAL RIVER - UNIT 3 3/4 5-3 4
t
- - - - - - - - - , - - - ___, _ l
CamTA!WENT SYSTEMS mileE16T AIR LOCKS- . . ,f ,
- ,. r... . .
{ .. .. . .
LIMITING CON 0tTION FOR OPERATION .
- 3.6.1.3 Each containment air lock shall be OPEltA8LE with:,, .-
... s,,.
a. Both doors closed except when the air lock is being used- fbr normal transit entry and. emit t ..m;. the contattunant, then at least one air lock door shall be closed, and
b. An overall air lock leakage rata.of <, .0.05.L, at P,. 49.6 psig..
APpLICASTLITY:. , PEDE5't . 2. 3 and. 4.-
ACY!ON:
With arr air lock incoerable, restore the air lock te.iFERAELE. status s.:. . -
within-24 hours or be in at least HOT STAN08Y within'the nent 4'hourf.'G "
and in COLD SHUTD0'm within the following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months . . -'< ,; i '.
SURVE!LLANCE REQUIREMENTS i
4.6.1.3 Each containment air lock. shall be. demonstrated 0PCIASLE

.-
I a.* After each opening, except when the air lock.is-taing used;for -
multiple entrtes, then et least once per 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months , by verifying --
m seal leakage 4 0.01 L when the volume between the door .
seals is pressurized lo 3,8 pstg, for at:least 30 seconds.:-
b. At least once per 6 months by conducting an overall air lock leakage test at P 49.6 psig, and by verifying that the overall air lock: leakage h,ts is within its limit. and. . -
c. At least once per 6 months by verifying that only one door in ,
each air lock can be opened at a time. .c Exefmtion to Appendix "J" of 10 CFR 50.
CRYSTAL RIVER - UNIT 3 3/4 6-5
--<---.-m _._. . .- _ .. ...__ . ._ __ _ _ _ _ _ __ __
$ g
W n EMERGEMgY FERDWATER SYSTEM
~
3.7.1.2 ' T== !. ' , r .. steem generseer emergency h.
piamps amo essestated fles pasha sheat he orERAaLE wine a.. one n r feedwater pump capahkr se hans pesaret.areer om. 'T' ';
opeaAaLL_e_mnergeacr hus,. amt .. - - -
h one emergener feedester pump capable eartmas pe=ared tram 'en optRAsLE steam supply system.
, ArrucAng, TTY 'ucoE1.1,2, and 3..
M *. .
l a.
With one emergency feedenour pump- andfer MW:ISour path '
1.- - w , restare the syssem se optRAsLE samem wuren. .'.l,, -
,,[i 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months er be in HOT WN withis the next 11 hours1.273148e-4 days 0.00306 hours 1.818783e-5 weeks 4.1855e-6 months . . ' i' - " -
SURVEE. LANCE REQUIREMENTT t -' . ' l" i ,_.,., [. >
e.,- s t
4.7.1. 2 Each emergency feedwater system shall be demonstratej OPERABLE '
a. At least once per 31 days by:
1.
Verifying that the steam turbine driven pump develops a discharge pressure greater than er equal to 1100 peig en recarcidatten tiew when the seenndary stemm suppiy preneure is greater:then 20er.
, psag,*
t
2. Verifying ther the minor *iven pump W a % -
presserscat yecame them.ar agema .se 1100 past en rm -
flow. .. .
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Then not in MODE 51, 2, or 3, surveillance shall ne performed within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months atter.
entering MODE 3 and prior to enfermg MODE. 2.. I l
I CRYSTAL RIVER - UNIT 3 3/47-4 ht No. IT.' 64 '
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3/4.8 ELECTRICAL POWER SYSTEM 5 0 SMA.1 K.C. 50URCES ,.- , a ;,
OPERSTIN8 .
l
. . ' LIMITINE wmniian FOtt vrivuun
. t _
s /
3.8.T.1 As a sinfaus; the foltaming-A.C.' electrical peer sources shelf
h e W irm a et r -
a. Two physically thdependent circuttschstwoon-the offsite crans-mission network and. the.onstte_ Class 1E distribution system, and- .
b. Two separate and independent-diesel: generators each with:. . .e .
1. A separate. day fuel. task contatning a.minir a values of 4W/.:1 gallons of fueli- . i:
2. A separate fuel storage systes containing'a.stnisson Y. . 4 volume of 20,300- gallons. of fuel. ~and.- !-
, J .i '.
3. A separate fuel transfer pump. -
APPLICA8!LITY: MODES 1, 2, 3 and 4.
ACTION:
I a. Witn either an offsito circutt or diesel genereter of the above ---
required A.C. electrical power- sources inoperstle, demonstrate -
the OPGASILITY ef'the remaining A.C. sourcan.by performing:
Surveillance Requirements 4.8.1.1.1.a and 4.8.1.T.2.a.4 within .
( one hour and et least ance per 8 hourr thereafter; restore.at least tuo offsite circuitr and two diesel generatott to CPERASLE.-
status mithis-72. hours or be-in at:1 east HOT STAN(NY within-the r .-
next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months ont in C0tD SHUTDOWR within the following 3O hours.t.,-
b.. .With one offrite ctreuit and one diesel generetor of.tNr sheverg required A.C. electrical power sources inoperable, demonstrate. . y, .
the OPERA 8ILITY of t* ; rensining A.C. sources by performing Surveillance Requirements 4.8.1.1.1.a and. 4.8.1.1.2.a.4 within '
- one hour and at least once per e hours thereafter; restare at.
i least one of the inoperable sources to OPERA 8LE status within -
1 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months or be in at least MOT STAN08Y within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months j
and in COLD SHUTOOWN within the following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months . Restore at least two offsite circuits and two diesel generators to 0FERA8L I status within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months from the time of initial loss or be in at least HOT STANCBY within tt e next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in COLD SHUTCCWM within the following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months . ;
l CRYSTAL RIVER - UNIT 3 3/4 8-1 1
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ELECTRICAL POWER SYSTEMS ,,,, , , , , ,
ACTION (Continued) , , , , , ,
'l j
l c. With tuo of the above rogstred offstte-A.C.' circuitr inoperetrie -
. demonstrata mm OPERASILIII of tua diaset meeretors.by-- .- . .
perfonning Surveillance Requirement 4.8.1. . Z.a.4 within enes. . . <.--
hour and at least. esca Jer. S_ hours. thereafter, unless thet 4 #M *'
diesel generators are alrea# operettas; restore at least one of the inoperable offstte sources tu #ERRKE status within-24^- ~
i hours or be in at least HOT STANORY within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .
Wittr only one offsite sinsrce restored, restore-at least two 1
, offsite circuits to OPERASLE. status within 71 hours8.217593e-4 days 0.0197 hours 1.173942e-4 weeks 2.70155e-5 months from time of initial loss or to.in at 1 east NET STAMSV within the neat - .
6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .ent.ta.CELSIRITIIBA within the:ftliesing 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months . .,
d. W4th two af-the-above required diesel generstors" inoperable. ,
demonstrata tha CPERASILITY.er. tuo offsite: A.C..circutts ty. . >,
l performing Surveillance Requirement 4.8.1.1.1.a.within.eme... ,
! hour. and at least~once.per S hourt thereafter;; restore tot " .
least one of the inoperable diesel generators D WESASLL-. ,'
status within 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months or he .in at.least HOT STAutR within the: - -
next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in COLO SHUTDOWN within the following 30-
hours. Restore at least two diesel generators i.o OPERA 8LE status within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months from time of initial loss or be in at least HOT STAN08Y within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .
SuitVEILLANCE~REQUIkummi' ,
4.8.1.1.1 Each. independent etrentt-between the offsite-transartssion- > "-
network and the anstto:Clast 1Ldistribution systes shall be:- -
a. Deterartned SPERREE'at toest once per 7 days by verifying;- -
i
1. Correct breaker elignments ant:1ndicated' power'evetlabilityN . '
and
l
2. That the sump pumps in the tunnel containing the DC
.. control feeds.ta the 230kw switchgear are OPERABLE : .
b. Demonstrated OPERABLE at least once per 18 months during -
i shutdown by transferring unit power supply from the normal.
circuit to the alternate circuit.
j CRYSTAL RIVER - UNIT 3 3/4 8 2 j .
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CATEGORY 5 4. ANSWERS'
. 2 . ,
f--
5.01- a. Increase (0.5)
b. Decrease (0.5)
c. Increase (0.5)
d. No effect '
(0.5)- 5 Ref: CR3 HTFF, pg 158 & 159 : . . t . .
5.02 a. Higher (more Xenon) (0.5)
b. Lower (less negative than used in calc.) (0.5)
c. Higher (Tave increases, more neg, reactivity) (0.5)
d. No change (no effect on Tave) (0.5)
Ref- NUS Manual.3, Section 12.5 To revent revenTraptdTdsT Gerrat c[$anges-in pressurfzer -Ja i rancT r ed 6d(1.0) 5.03 To .
level from occurring due to bueble formation in the . H-vessel head.
Ref: HTFF, CR-3 Draft Manual 5.04 a. Inserted -
(0.5)i' 't
b. Inserted (0.5)
Ref: APSR Integral worth curve at 0% FP, ARO' - .
5.05 a. Pressure boundary (0.5)
b. ONBR (0.5)
c. DNBR (0.5)
d. ONBR (0.5)
Ref: T.S. 2.1, Safety limits bases 5.06 a. Increase (0.5)
b. Oc:rease (0.5)
c. Increase (0.5)
d. Increase (0.5)
Ref: NUS Module 3, Section 8.4 5.07' a. More (0.5)
b. Less (0.5)
Ref: NRC G&W.Systes Manual, p. 8.1 -
i ghh 0 A,..... (4) -
-( 1.0) -
Ref: HTFF, 83.3, p 355 5.09 Answer (a) False TS 3/4 2-5 & 2-7 (0.5)
(b) F. M TS 3/4 2-11 Tf?.u s~ W (0.5)
(c) True TS 3/4 B2-1 (0.5) t 1
g 5.10. . Answer (c) 2.- .. .
( 1.0 ) .' -
.Refe ICS Analog & Digitals-5.1L Answer True (0.5)
Ref: NTFFS. 151 ,
5.12. . Answer (a) True p. 10 (0.5)
(b) True p. 2 (c) True pp 2-3 (d) False p. 7 Ref: Analysis Susanary in Support of an- Early RC Pump-Trip B&W Submittal - August 24, 1979.
5.13 Answer: Based on the maximum time within which a . trip must ( 1.0) ' !4 occur to provide DN8R protection for the four pumps -
coastdown Ref: TS.p. 82-7' 5.14 Answer (a) DECREASE (0.5) -
(b) NOT CHANGE (0.5)
(c) DECREASE (0.5)
(d) 0:CREAS tO& e tf W (0.5)
Ref: HTFF, Section 2, p. 57 5.15 Answer: 1. Zirc water and metal water reaction (0.5) -
(Zr + 2H,0 + Zr 0, + 2H,)
2. Dissolved H, (0.5)
(will come out during depressurization)
3. Radiolytic>decomposttton of water (0.5)
(2H2 O + 2H, + 0,)
4. Aluminum plus Sodium Hydroxide water solution - (0.5). .:
(2A1 + 2 NaOH + 2H,0
2NaA10, - 3H,) -
Ref: HTFF, Section of Reactor Heat Transfer and Themal .
Hydraulics 5.16 Answer b. CR1/CR2 = 1-k2/1-k1 for a tripled count rate (1.0) and a Keff=.95 K2 = 1 .01665 = .98335
.0335/.05 = .67 - 2/3 Ref: NUS, Vol. 3, pp 12.1-4 8 I
3 5.17 An e d e.for 0-5 assemblies,1/M = .571 (1.0),~ .* .* ..<
. for 0-10 assemblies,.1/M = .444 V -
. .. .. . ! - ' for 0-15 asseselies, 1/M = .348 for 10-15 assembites,1/M = .782
<- :. See attached graph for curves -
h
Ref: NUS, Vol. 3,linits 12.2,.12.3. ,
't
. .. , i s.
5.18 Answer d (1.0)
Ref: NUS, Vol. 3, Units 9.4, 9.5 i
e 9
o e
ee f
! [__ '_..
4
~'
. , 3; CATEGORY 6..- ANSWERS ..
8 6.01- Answer: ,-(1) Grapple unloaded core (2.0)
(a) Grapple disengaged-
-(b) . Grapple over core 6 (c) Grapple elevatten less than 125 feet --
. c
,y .. .. -
(2) Grapple Loaded Core (a) Grapple engaged (b) Grapple over core (c) Grapple elevatton less than 139 feet (3) Transfer Area (a) any time grapple is over racks. r Ref: STW 21-48 Msc) Aaz Mles '3-3,3 'i M 3-T (S"9 -i 6.02. Answer: . (1) the fuel grapple must be up .i * . - '>(0.5)l~ it.
(2) the TV cylinder must be up or bypassed. - -
(0.5)> t " -
(3) the control rod tube must be up (0.5)
(4) the control rod mast must be in the orifice (0.5) retracted position or the telescopic cylinder must be fully up Ref: STM 21-39 6.03 2 - are located on the Remote Shutdown (0.5)
Danel - 2nd floor of Control Complex outside of
'B' 4kv Switch Gear Roon 1 - inside 'A' 4kv ES Switch Gear Roon (0.25) 1 - inside 'B' 4kw ES Switch Gear Room (0.25) -
Ref: Remote Shutdown Panel, MAR Training,- 77-07-01, pg 1 ,
- i,
. 6.04 Answer: a. Iow exhaust hood temperature (1.0) .
. $. . Ref: STM 27-72 6.05 Answer: (1) (closes WDV 439)
(waste gas discharge auto control valve) (0.5)
(2) (closes WDV 393, 394 and 395)
(waste gas decay tank outlet to recycle valves) (0,5) '
Ref: STM 41-4
_ Q_ l
5 6.06 .- Answer:.' a.. Mcdulating solenoid valves that use an t R-
,' , ., . increasing DC current opposing spring pressure. (0,5) . i "
b .. Fati in full open posttion on a loss of power. (0.5)
'. c. . No provtsions for any local or manual . control . (0.5)
- Ref:. Lesson: EFW and EFIC;.ANO-113,p. 8 & 9 . ?. . '. '<.-h
' t i' 6.07 Answer: EFV-1 and EFV-2 are interlocked such that they can be open only 1f at least one of the two DC powered condenser vacuum breakers is open. (1.0)
Ref: Lasson: Emergency Feedwater and; EFIC, ANO-113,. pg 2
6. 08 '- Answer. (1) after 150 minutes idle time "
(0.5) s (2) after 25 minutes running time (0.5) '
t
'te f : STM 2-105-6.09 Answer: >15 hours (0.5)t
1 Ref: OP 404, ste 4.2 '
6.10 MCC 3A3 119' Elev (Aux aldg) in Corridor near MCC 3A2 - Directly East of Spent Fuel Pools (0.5)
MCC 3B3 95' Elev ( Aun Bldg) Outside MuP area (0.5) .
Ref: Lesson No. MAR 80-05-14-03 6.11 1. 50 psig (0.5)
2. 125 pstg. (0.5)
. 3. 50 usig (0,5)
4. O psisj. M g p'g (0.5)
Ref: STM TH 504, pg 49 & 50 6.12 a. No runback. (0.5) LJad limit for 3-RCP's is 755 ( O '. 5 ) ' ', '. ' " . -
(page 12)
. . b. FW will reratto. (0.5) Total FW demand signal is modified by delta between Loop A and Loop B RCS flow (see diagram page 72) (0.5)
Ref: STM CH 504, pages noted above.
.1 1
6 6.13 a7 ,1. ./ HPI Block 3 and- Block B actuated on 2 out of 3 channels .;**.
(RC-1, RC-2, RC-3) or (0.5)
' 2. ' HPI bypassed af ter an actuation on 2 out of 3 channels (RC-1,RC-2,RC-3) (0.5)
b. 30 psig signal-[2.of 3 channals RB-4, RS-5, RB-6] (0.5) c.. 1. 2 new reset pushbuttons on ESF-A&& sections of main.- -
.- v i. * .
control board (0.5)
2. If HPI is bypassed and the associated ES 4160V bus.UV relays actuate, the permit will be automatically reset. (0.5)
3. If HPI is bypassed and is then reactuated by either LPI or RB 150 and COOLING, the permit will automatically be reset. (0.5)
Ref: MAR TRAINING, 882-05-01-CI .E5 LOGICJPODIFICATI W , pg 2' & 3 ..
6.14 a. Ensures that the TBV's remain closed on a loss of power. ( 1.0) . ?
b. On loss of CW pumps or low vacuus,. the ICS will close the > . .. .-; '.
TBV's. (Circuitry in the ICS that shifted header pressure
e control to ADV's [for loss of CW pumps and low. vacuum] hasa...
eeen removed.) ( 1.0) a Ref: Lesson No. 77-07-01-11 6.15 a. Reactor power must be >20% for auto initiation on loss of both main FW pumps (pg.14) (0.5)
b. 1 of 2 Taken Twice logic - Only one bus relays i are energized-(pg 13 - Fig. SA) (0.5) hg& .g EFIC is manually bypassed (loss of all RCP initiation) when reactor power is <18%. (pg 14) (44}
d. Initiation of EFW reoutres HPI actuation of Both A & B.
ESAS channels.. (pg .14) . (0.5)
Ref: ANO-111 Emergency JW & EFIC pp-noted .above. ?
6.16 a. Highest of '4 Power Range NI's (0.5)-
b. Average of 5 highest incore readings -
(12 incare inputs into SPOS) (0.5)
. c. Source Range count ' rate >1000 cps, Me r n m a. -tw (.25) an_1 all rods are vwT6 a se c. atte r rn p (.25)
d. The SPOS display will automatically switch to the Post-Trip Screen (.25) with the history trace on (.25)
Ref: MAR Training, SPOS t
I f
s I 7
( .. . s ,; , + CATEGORY 7 - ANSWERS ., - ./ ..A
' e
. g . .
7.01 J Answer:4 LBPR.' R i!Il w e r y (0.5) s
Source Retainer (0.5)
. Ref: FP-203,- Step 5.1.10 .
7.02. Answer: Valve breaker handle place in " Lock-Reset" positfon - ., .t - '. c';
' ~
(OHV-3) CH Removal Outlet. (0.5)
(OHV-4) CH Removal Isolation (0.5)
(OHV-41) DH Removal Outlet Contatnment Isolation (0.5)
Controlled by the 5.5. and are blue taqued (0.5) .
Ref: OP-404, Section 4.10 f .r 7.03 Answer: (1) Valve to Fire hose station adjacent to pit.ts -
. */3 closed ( 0. 5).
(2) Noz:le on hose is closed . -
(0.5)*.. -
'l (3) No foaming' attachments are present- (0.5) a Ref: FP-302, Rev. 18 Step 4.25
- 7.04 (1) Raise to " Grapple Tube Up" position --(-M)--
(2) Verify " full up" on ZZ Tape -(.20)--
, , D(b (3) Pull out spring loaded lock pin (4) Use ratchet handle to rotate. 90* ,
-(.20)
.J_ 2n).
g (5) Release locking pin ,
0.20)- .
i Ref: FP-601, Rev. 18. Stoo 9.8 7.05 answer: a. ALL . (0.5)
b. (Q)(R)(A) (0,5)
c. None (0,5)
d. 5 hours5.787037e-5 days 0.00139 hours 8.267196e-6 weeks 1.9025e-6 months (0,5) -
s. .
Ref: EM-203, Rev. 14, pp 4 & 5
- EM-207, Rev. 18, pp 15 I 9
g 7.06 - 3 ar' 1... Ensure turbine runback "
i ,
2., Ensure RC stable (1.0) s 2 NOTE:'"' All but AP-542 say " Ensure control rods inserting",
AP-542 says " Ensure NI power lowering." ,
b' . Ensurer (1) affected MFP tripped 2 . <>
(2) OPEN - FW-28 (cross-tie) .- '.- -
(3) CLOSED - FWV-29 and FW-30 (4) control rods inserting (1.0)
c. 1 - 55% -d 11 - 55% -d 111 - 60% -c iv - 705 -b (1.0) 7.07~ a. Radiation Work Pemtt, '
(.25) T' Shif t Supervisor (.25)
b. 2 (.25)..: -
. I hr (.25)
c. Sound containment evacuation alarm. (0.5).' -
Ref: OP-417. Rev. 38 pgs 4 and 36 7.08 1. Bypass ES Actuation (0,5)
2. Return ES Equipment to Standby status (0,5)
3. Go to VP-580 (0.5)
Ref: AP-380, Rev. 04, pg. 3. -
7.09 a. If suecooling eargin is inadequate ( 1.0)
? 1500 psig 20*F 5 1500 psig 50*F
b. If all RCPs have not been stopped within (1.0) two minutes, they must be kept running .
i Ref: AP-380, Rev. 04, pg. 4 7.10 Answer: (.25)
fa.b. 21552100Vd(
j 579 3.5'F (.25)
c. 568 2 3.58F (.25) '
' d. 590 z 3.5"F
(.25)
e. - 900.1 fogs 4, [%g gsta.) (.25)
f. 588 2 5*F (.25)
Ref: OP-204, Section 2.0 b\\tHM .t 2.*f at .cpj s.p w & dsl* A+ A Tl'N .t/pp n_do4awa..
_ ________._______L___f________._________________.__.__________._____________._
s
. g 4 u 7.11 :: a. A0 pen, Locked Reset, Locked (.75)' r. . ;
b.
(0.5)
. , eg.l .'69Closed, Locked Reset,
(.25)
, ,. Ref:],0P-401' 7.17~ Answer: True - (0.5) a Ref: OP-202, Step-6.3.2.
7.13 OTSG 'A MSV-411 & 412 (MSIVs) '
FWV-30 (MBV) -
FW-31 (LLBV)
FWV-36 (SUBV) di FWV-28 . -(Cross-tfe) -
FWV-14 (FWP Suction) -
FWV-35 -
(EBV) - '~
"0TE: ' O.;. 3 "5"-55. -
NOTE: Step 4 - Ensure Closed- '
MSV-9 & 10 (TBVs)
'iSV-25 (ADV) :-
(0.2 ea)
Ref: AP-460, Rev. 02, pg. 2 7.14 NOTE: OP-502 Step 12.1 says to refer to Section 7.1. This section addresses Safety Group Transfer from DC Hold to Auxiliary.
}
a. Select: All (Optional), -
(0-) L O*'f I)\ M u RG L. <
c E ,. Manual- $elcct- M. AvP Selec _ . SEQ-OR- ' . [ ((.2).2) 994 Ata ( p Select:.
Select:. G um /
-desi d.-
(.2)
(.2) -5deth AW Depress-Transfe seti (.2) 5 \ c ty S Eu, -oC ,
Select: Jag (.2) <g-ett ~~Io C r-r anual Transfer. (. *T N Press- Clamp Rel .2)
O h\ ret COM9 ' . .. .
- Prys : Group (. Y 3c\<ct tA M u t- V M 5 M L Miect: Run, if desired (0 6 5+>v d CW9 9.ETW '
* "eJe GCt,J .
Ref: OP-502,Rev.17, Step 7.1.1.through7.1.M'tt't Rut 4 (.d.
b. Trip 9.eactor AND (.5) '
go to AP-580 (.5) ,
7.15 Answar: b
\' Ref: OP-501, Rev. 8, pg. 3. ~
ear
10

T P 4 -
i CATEGORY 8 - ANSWERS - .
8.1 Answer
-c- ,
(1.0)
Ref: OSIM.VI-4 -
8.2 Answer
No. OSIM P61f cy (Step'B.1) doe's not permtt sign-off for - (I.0) ..I t, a red-tagged.ites.in. ether than.the.specified canditJon. s. * * . 3 %
Ref: OSLR VI-1.
8.3 Answer
(1) Block valve (RCV-11) must be operab.le (1.0)
(2) Must-have a dedicated operator (1.0)
.Ref: OSIM V-ZZ
8.4 Answer
- No. He- must remain within visual . contact .. (1.0)' &
of control-board.unless relieved. .
Ref: OSIM-I ..- -
4 8.5 Answern- (1). . Single line thru incorrect:entryr .
( . 33P.'. : ' '
(2) Enter correct information adjacent to (.33) ?
or' in a space available with reference to deleted entry (3) Individual making correction shall (.33) initial and date error correction
8.6 Answer
a. True . (0.5)
b. False (independent.verificattom required) (0.5)_- -
c. False (10 minutes)- (0.5)
d. False (only safety. group 1) (0.5)
. Ref: OSIM'III-9 ~.III-10'.and IV-ZE
8.7 Answer
a. (1) .If the S;S. declares.the PORV inoperable . (1.0).
90200 then 0300.
(2) If' the S.S. does not declare PORV inoperable. '-
@0200 then 0330 -
b. (1) Hot standby within 7 hours8.101852e-5 days 0.00194 hours 1.157407e-5 weeks 2.6635e-6 months from time stated (1.0) in part a.
c. Yes. Provisions of 3.04 are not applicable. (1.0)
Ref: TS 3.4.3.2 a
(
U 'T 1
11 8.8 . Answer:. ai.
n' _. ,
(1.0) , .' -
Ref: EncionedTS- ,
f. 8.9 Answer: -a. 12 .
b. 12 .
c. 7 .
.- d. 14 . .
(0.5 each)
Ref: OSIM IIL-5 8.10 a. To. predict the trajectories _and dose rates . (1.0) of radioactive matartal released from the plantr.-- .
b. (1) F1 - Emerge / Accident Control' (0.5) . 't (2) F4 - Dose Assessment? (0.5)- -
T 8.11.(1). Emergency Classification . ( 0. 5). . . +l '
(2) Noti fication .
(0:5):.' * .
(3) Protective Action recommendations to' State and local (0.5)' ?
authorities responsible for offsite emergency measures Ref: EM 202, Rev. 21, 3.4 8.12 Answer: 1500 Hours (1.0)
June 3,.1985 Ref: TS'3.0.~3 Bases.
8.13 Answer:. No. (1.0)
Changing modes is not. allowed by.TS 3.0.4 Ref: RS 3/4 4-4 8.14 Answer: b.: (1.0) .
Ref: TS 4.0.2
.. 8.15 Answer: a. 4 (0.5)
b. 2 (0.5)
c. 2 (0.5)
d. 1 (0.5)
Ref: TS 3.4.6.2 I f .
o .. -
s
- ,= 12 8.16 Answer: caa Yei.-. Note 2,. Table 3.4-24 -
(1.0) '
2 gpm is less than 1
> ed. .- . [ 2.5 gpm 50% of band
7. i. *
'," i~ b. Note 3, Table 3.4-2 (1.0)
'a reduce - to. within limits within 4 hours r' A .*
or be irr het standby withtrr following 1
. i ,
8.17 Answer: %nd -72. (1.-)-
O' Ref: TS'4.6.1.3, Appendfx J (MuAt Kwo Aryx .T t wM bt04) 8.18 Answer:- Cold Shutdown (5) (0.5)
Ref: T5'1.0 Definitions O
T
. . UNITED STATES
,y[pnt!
o NUCLEAR REGULATs2RY COMMISSION p ,
o CEllON il e 101 MARIETTA STREET,N.W. )
E f ATLANTA,CFORGI A 30323 /
~s.,*****/ ENCLOSURE 3 U. S. NUCLEAR REGULATORY COMMISSION REACTOR OPERATOR LICENSE EXAMINATION Facility: Crystal River Unit 3 Reactor Type: B & W 177 Date Administered: November 21, 1985 Examiner: D. Falconer Candidate:
INSTRUCTIONS TO CANDIDATE:
Use separate paper for answers. Write nswers on one side only. Staple question sheet on top of the answers sheets. Points for each question are indicated in parenthesis after the question. The passing grade requires at least 70% in each categ and a final grade of at least 80%. Examination papers will be picked up four hours after the examination starts.
% of Category % of Candidate's Category Value Total Score Value Category 25 1. Principles of Nuclear Power Plant Operation, Thermodynamics, Heat <
Transfer and Fluid Flow i pC g '
2. Plant Design Including Safety and Emergency Systems N' X 3. Instruments and Controls 25 4. Procedures - Normal.
Abnormal, Emergency, and Radiological Control Y.Ig TOTALS Final Grade %
All work done on this examination is my own. I have neither given nor received aid.
Candidate's Signature
4 CATEGORY 1 - PRINCIPLES OF NUCLEAR POWER PLANT OPERATION, THERMODYNAMICS, HEAT TRANSFER AND FLUID FLOW (25.0) 1.01 The reactor is brought to 10 ' amps during a Xenon free
[MC] startup. In order to maintain power level at 10 ' amps for about one hour, what will have to be done with the control rods? (Assume no other reactivity effects). (1.0)
a. They will have to be withdrawn as Xenon builds in.
b. They will have to be inserted as Xenon burns out.
c. They will have to be withdrawn initially then inserted to compensate for Xenon.
d. They will remain at a constant position because Xenon effects are negligible.
1.02 During a LOCA with a resultant loss of subcooling
[MC] margin, Reactor Coolant Pumps (RCPs) are secured for which one of the following reasons: (1.0)
a. To prevent pump damage resulting from operation under two phase conditiens.
b. To prevent core damage resulting from phase separation upon subsequent loss of RCS flow.
c. To reduce RCS pressure by removing the pressure head developed by the RCPs.
d. To remove the thermal heat being added to :he RCS by the operating RCPs.
1.03 Indicate how natural circulation will be affected by each of the following situations. Consider each one separately and answer INCREASE, DECREASE, or NO EFFECT.
a. Reduction of turbine bypass valve setpoint (0.5)
b. Decrease in OTSG 1evel (0.5)
c. Reduction of feedwater temperature (0.5)
d. Increase in RCS pressure (0.5)
[ .
a 2
1.04 An ECP is calculated for a reactor startup four hours after a reactor trip from 100% equilibrium conditions.
For each of the following situations, indicate if the actual critical rod position would be HIGHER, LOWER or NO CHANGE from the calculated critical rod position.
Consider each situation separately and assume no other changes.
a. The startup is delayed until eight hours after the trip. (0.5)
b. The actual boron concentration is 50 ppm lower than that used to calculate the ECP. (0.5)
c. Tavg is 535 F as compared to the value of 532 F used in the calculation. (0.5)
d. OTSG level is stable at 40 inches on the startup range. (0.5) 1.05 During a reactor startup, eaual increments o'f reactivity
, are added and the count rate is allowed to reach equilibrium each time. Choose the bracketed word (s) that describe what is observed on the Source Range indication and/or Startup Rate (SUR) meter.
c. The change in equilibrium count rate is [ larger]
[the same] [ smaller] each time. (0.5
b. The time required to reach equilibrium is [ longer]
[the same] [ shorter] each time. (0.5)
c. The point of supercriticality can be identified by a(n) [ increasing] [ constant] [ decreasing] positive SUR several seconds after the reactivity addition is terminated. (0.5) 1.06 Which one of the following parameter changes will increase
[MC] the Departure from Nucleate Boiling Ratio (DNBR)?
(Consider each separately). (1.0)
a. Reactor Power Increases
b. RCS pressure Increases
c. RC5 Temperature Increases
d. RCS Flow Decreases
3 1.07 The unit is operating at 50% load. Each steam
[MC] generator has 100% loop reactor coolant flow and 50% of the total loop feedwater flow. If loop 'A' loses one of the Reactor Coolant Pumps;
a. the resulting primary flow would be: (% of loop flow) (1.0)
1. loop A < 50%, loop B > 100%
ii. loop A = 50%, loop B = 100%
iii. loop A > 50%, loop B < 100%
b. the feedwatar flow, to satisfy the ATc controller would be approximately (1.0)
1. loop A = 36%, loop B = 14%
11. loop A = 25%, loop B = 25%
iii. loop A = 14%, loop B = 36%
1.08 Which of the following statements is correct if the
[MC] discharge valve from a centrifugal pump is being ,
partially c'osed from the full open position? (1.0)
a. Pump head decreases as head loss decreases. 2
b. Pump head increases as head loss increases.
c. Volume flow rate increases as head loss decreases.
d. Volume flow rate decreases as head loss decreases.
1.09 The decrease in the effective delayed neutron fraction
[MC] over core life is due to: (1.0)
a. The reduction in boron concentration.
b. The half-life of U-235.
c. The more negative MTC.
d. The buildup of Pu-239.
. ~
1.10 Why should RC cooldown on natural circulation not exceed 10*F/hr for Tc >280 F? (1.0) 1.11 Which one of the following is N_0T 0 expected to be a
[MC] source of Hydrogen gas accumulation in containment following a LOCA? (1.0)
a. Metal-water reaction involving the Zirconium fuel cladding and the reactor coolant.
b. Reaction of austenitic stainless steel components with boric acid.
c. Radiolydic decomposition of the post accident coolant.
d. Corrosion of metals by building spray water.
1.12 Delayed neutrons play a major role in the operation of
[MC] the reactor because they ... (1.0)
a. are born at thermal (slow) energy levels and are therefore more apt to cause fission as compared to being absorced by a poison.
b. provide approximately 70% of the fission neutron inventory and have a higher importance factor associated with them as compared to prompt neutrons,
c. are corn much later than prompt neutrons and therefore effectively lengthen the average neutron generation time.
d. are considered epithermal neutrons and therefore have a smaller probability of leakage than the fast and thermal neutrons.
1.13 Assume that the reactor is at 100*. power, beginning of life, with Group 7 rods 90*. withdrawn. Indicate if Group 7 must be INSERTED or WIT liDRAWN to maintain the reactor at 100*. power for the following evolutions.
(See APSAR Worth Curve, I!; r; 1.1], attached).
3.'l
a. the insertion of Group 8 from 36*. to 15*.. (0.5)
b. the withdrawal of Group 8 from 50*, to 80% (0.5)
5 1.14 Indicate if either DNBR or Pressure Boundary protection are provided by the following Reactor Protection System Trips.
a. RCS Pressure-High (0.5)
b. RCS Pressure-Low (0.5)
c. Reactor Coolant Pump Power Monitors (0.5)
d. Nuclear Overpower Based on RCS Flow and Axial Power Imbalance (0.5) 1.15 Indicate if the severity of the following accidents INCREASE or DECREASE with a positive moderator temperature.
coefficient.
a. Rod Ejection Accident (0.5)
b. Steam Line Break (0.5)
c. Loss of Feedwater (0.5)
d. Rod Withdrawal Accident (0.5) 1.16 Tcold and Group 7 insertion affect the excore power range calibration. Indicate :f reactor power determined by the excore detectors will be LESS CONSERVATIVE or MORE -
CONSERVATIVE with the following conditions,
a. increasing Tcold (0.5)
b. inserting Group 7 (0.5) 1.17 The unit is in Mode 3 (Hot Standby) at the middle of core life with groups 1-4 withdrawn to 100%. If the reactor is shutdown by -4% AK/K, indicate if the amount that the reactor is shutdown INCREASES, DECREASES or REMAINS CONSTANT under the following conditions?
a. The RCS boron concentration is decreased by 20 ppm. (0.5)
b. The steam pressure setpoint is increased from 1035
.. psig to 1070 psig (0.5)
c. RCS pH is increased by adding lithium hydroxide (0.5)
d. Group 5 is withdrawn to 100% (0.5)
6 1.18 Assume that the reactor is subcritical by 1.0% AX/K.
Groups 1-4 are 100% withdrawn and Groups 5-7 fully inserted.
Indicate if the required Tech Spec shutdown margin is LESS THAN, GREATER THAN or E0 VAL TO 1.0% AK/K. (0.5) 1.19 In an under moderated core, indicate if an increase in fuel temperature INCREASES or DECREASES the magnitude of the following coefficients.
a. Moderator Temperature Coef ficient (0.5)
b. Fuel Temperature Coefficient (0.5)
END OF CATEGORY I
7 CATEGORY 2 - PLANT DESIGN INCLUDING SAFETY AND EMERGENCY SYSTEMS (23.0) 2.01 Transfer switches are used to transfer control from the control room to the Remote Shutdown Panel. List the location of each of these four switches. (1.0) 2.02 When the transfer switches are placed in the 'RSP'
[MC] position, which statement is correct concerning components necessary for shutdown of the plant? (1.0)
a. Control circuits from the control room are isolated, but ES signals are not defeated,
b. Control circuits from both the control rocm and the RSP are activated, but ES signals are not defeated.
c. Control circuits from the control room are isolated and ES signals are defeated.
d. Control circuits from both the control room and the RSP are activated and ES signals are defeated.
2.03 TRUE or FALSE ,
The diesel generator auto start feature on under-voltage is still active when the transfer switch is in the RSP position. (0.5) 2.04 Two AC oil pumps are provided to supply oil to the feedwater pump / turbine. State the purpose of the third DC Lube Oil Pump. Indicate auto start setpoints. (1.0) 2.05 How many hours does the minimum water volume in the condensate storage tank ensure that the plant can be maintained at Hot Standby conditions with steam discharged to the atmosphere concurrent with a loss of offsite power? (0.5) 2.06 To start a fourth reactor coolant pump, the cold leg temperature must be greater than 500 F. Explain the bases for this interlock. (1.0) 2.07 According to the STM for Core Flood Tanks, what is the most important reason that Core Flood Tank pressure is carefully controlled? (1.0)
8 2.08 Which of the following is NOT a Main Feedwater Pump Trip. (1.0)
[MC]
a. Low exhaust hood temperature
b. Low lube oil pressure
c. Loss of governor speed signal
d. Both feedwater booster pumps tripped 2.09 TRUE or FALSE (0.5)
The idle gland exhauster auto starts on low gland exhaust pressure.
2.10 Answer the following TRUE or FALSE concerning the Nuclear Services Booster Pumps and CRD Cooling System.
a. One pump is normally operated with the other serving as backup. A drop in line pressure (25 psi) will start the idle pump. (0.5)
b. On an ES signal, the supply and return valves will close to the CRDM coolers and the booster pumps will have to be manually secured. ( 0. 5)~
c. SWP-2A is powered from ES MCC 3A2 and SWP-2B is powered from ES MCC 3B2. (0.5)
d. Low level in the SW surge tanks will trip the NS booster pumps. (0.5) 2.11 List the automatic actions that occur on a high radiation signal as detected by RMA-11 (waste gas decay tanks discharge to the auxiliary building ventilation system monitor). (1.0) 2.12 Which of the following is NOT supplied by the
[MC] secondary services closed cooling water system. (1.0)
a. Exciter coolers
b. Isolate phase Bus Duct
c. Gland Condenser
d. Feedwater Booster Pump Oil Coolers i
I
9 2.13 Answer the following with respect to the newly installed EFW flow control values; EFV-55, 56, 57, 58.
a. Mode of valve operation (AC, DC, air, or other) (0.5) l
b. Failure mode (open, closed, As Is) (0.5)
c. Means for lo:al or manual control (if any). (0.5) 2.14 What is (are) the interlock (s) that ensure condenser l vacuum is broken before the EFW pump suction can be shifted from the CST to the hotwell? l (1.0) l 2.15 Answer the following questions with respect to the pressurizer heaters.
a. Which busses supply power to pressurizer heater MCC 3A & 3B (0.25)
b. How many banks are modulating (0.25)
Qh 9
-e-- How many individual heater elements are contained in a bundle 'C.25)
d. If the normal power to the cressurizer heaters is unavailable, what is the alternate supply. (
2.16 Which cooling water system supplies cooling water to the reactor building spray pump motors? (1.0) 2.17 Which of the following will N_0T0 be found in reactor
[MC] building spray water. (1.0)
a. sodium hydroxide 1
b. boric acid l
c. potassium sulfate
d. lithium hydroxide
?.18 Explain how the emergency feedwater system promotes
.. natural circulation mcre so than normal feedwater. (1.0) 2.19 The reactor coolant pump motor may be started three (3) times successively from ambient temperature or twice from rated motor temperature. Additional repetitive starts are governed by motor operating temperature.
In the absence of thermal devices to determine both rotor and stator temperatures, what are the guidelines for repetitive starts? ( 1.0)
10 2.20 Describe how the 'A' and 'B' spent fuel pools can be isolated from one another. (1.0) 2.21 Maximum flow for the DH pumps is 4000 gpm. Minimum flow is 80 gpm. What is the maximum time that the DH pump can be allowed to operate continuously in the recirculation mode (80'gpm - 100 gpm). (0.5) 2.22 TRUE or FALSE The mechanical overspeed trip mechanism on the turbine driven emergency feedwater pump can be reset from the control room. (0.5) 2.23 Why shouldn't hydrazine be added to the RCS during operation of the make up demineralizers? (1.0) 2.24 New ES MCC's have recently been installed at Crystal River; MCC 3A3 and MCC 383. State the location of each of these MCC's. Include Aux Bldg elevation and reference a nearby piece of equipment or structure. (1.0)
END OF CATEGORY 2 9 .
- l l
11 CATEGORY 3 - INSTRUMENTS AND CONTROLS (25.0) 3.01 The turbine bypass valve / atmospheric dump valves may be biased by a O psig, a 50 psig or a 125 psig signal. Indicate which of these bias' apply to each of the four situations below.
1. The reactor and turbine are not tripped, the turbine bypass valves are closed, and header pressure deviation is less than 10 psig. (0.5)
2. The reactor is tripped as indicated by a TRIP CONF light on the Diamond Panel. (0.5)
3. The reactor and turbine are not tripped, and ULD is greater than 15%. (0.5) 4 The reactor and turbine are not tripped, and ULD is less than 15%. (0.5) 3.02 The Unit is at 70*. load with the ATc Controller in Manual (hand). One RCP trips. Answer the following,
a. Will the Unit run back? Why or why not? (1.0)
b. Will feedwater reratio? Why or why not? (1.0) ,
3.03 Fill in the blanks concerning the Integrated Control System I (ICS).
a. During a reactor startup with the Diamond Control Station and the Reactor Demand Station in auto, reactor power is now controlled using the control station. (0.5)
b. When load is between 15 to 18*., the OTSG's will lift off low level limits when the error is greater thai.
error. (0.5)
c. When a startup control valve reaches the 80% open position, a limit switch causes its respective to open. (0.5)
d. With two MFW pumps running and individual loop FW demand reaches 50'. the main block valve is signaled to open.
As soon as the bl sck valve leaves its closed limit.
i. The loop valve freezes its position. (0.5)
11. The nain feed pump switches from control to control. (0.5) 3.04 List four signals that will automatically shut the main feed-water block valves. (2.0)
12 3.05 The syn:hroscope is rotating slowly in the FAST direction.
[MC] Which sta ement is correct concerning the voltages and currents of the Incoming (Diesel generator) and the running (4kv bus)? (1.0)
a. Incoming and running are in phase, frequency of incoming is higher than running.
b. Incoming and running are in phase, frequency of incoming is lower than running.
c. Incoming and running are not in phase, frequency of incoming is higher than running,
d. Incoming and running are net in phase, frequency of incoming is lower than running.
3.06 Refer to Figure 3.06 which shows one of the Decay Heat Control Units.
a. Match five of the letters on the Figure (a through f) with the following descriptions of each indicator / controller.
NOTE: No correct answer for one letter. (1.5)
1. Increases setpoint value when moved upward and decreases setpoint value when moved downward.
2. Indicates value of measurement deviation from -
the setpoint.
3. Indicates value of the setpoint.
4. Glows dimly when power is on and is extinguished when either the +15v or -15v de supply fails.
5. Indicates value of remote input.
b. How do DHV-110 and DHV-111 respond to a DH pump Trip if this controller was in the automatic mode? (0.5)
c. Describe the difference between the DH valve control units and Building Spray (BS) valve control units. (What is the additional control feature on the BS units?) (1.0)
13 3.07 MAR 82-05-01-01 has replaced the existing RB spray actuation circuitry with a new system.
a. List the two sets of conditions, either of which will result in an RB spray PERMIT. (1.0)
b. In addition to the kB Spray PERMIT, what other signal is required for an RB Spray ACTUATION? (0.5)
c. The RB Spray PERMIT, once set, can be reset in anycne of three different ways. List each of these three ways. (1.5) 3.08 Answer TRUE or FALSE to the following statements concerning ASV-204 and ASV-5 (Steam supply valves to turbine driven EFW pump).
a. When both red and green indicating lights are lit, it could mean one valve is fully open and the other is not but you have no way of remotely determining which valve had opened. (0.5)
b. The new valve, ASV-204 was installed in series with ASV-5 to provide redundancy for main steam isolation signals. (0.5)
c. The position indicating lights on the PSA panel, on the local control station and on the RSP are common to both valves. (0.5) <
3.09 MAR 77-07-01-11 resulted in changes in the Turbine Bypass Valve and Atmospheric Dump Controls,
a. The existing -10 to +10 VDC control scheme for the TBV's was changed to a 4 to 20 milliamp DC scheme.
What was the purpose of this modification? (1.0)
b. Explain the ICS interlocks (s) between the TBV's/ADV's and loss of condenser vacuum. (1.0) 3.10 Answer the following concerning abnormal RCP operation.
a. What two control room indications of abnormal RCP operation, require the pump to be shutdown immediately? (0.5)
b. What control room indication of abnormal RCP operation, requires power level to be reduced to 72%, at 30%/ min, then tripping the affected RCP? (0,5)
14 3.11 The EFIC system will automatically initiate EFW upon detection of various abnormal conditions. For each of the following situations explain the reason or interlock that should prevent EFW from automatically initiating.
a. Reactor power is 10% and the only operating feedwater pump trips. (0.5)
b. Power level is 100% and the signal from OTSG 'A' " Low Range" level fails to 0. (0.5)
--c--- During plant heatup (RC Temp ~ 450 F), the three operating
%,pu> RCP's trip. - (0.5)
d. At full power an I&C technician causes an HPI actuation of ESAS Channel A only. (0.5) 3.12 TRUE or FALSE
a. It is impossible to return to the " auto" mode on the control rod drive panel if a safety group rod is off its "out limit" position. (0.5)
b. The " auto" mode on the control rod drive panel can be selected with " Sequence Inhibit" indicated. (0.5) 3.13 Answer the following concerning the Safety Parameter Display System (SPOS). See Figures 3 and 5 attached.
a. Which NI, or combination of NI channels, provide the indication for "% PWR"? (0.5)
b. Which incore, or combination of incores, provide the indication when "Incore Temperature" is selected? (0.5)
c. Following a reactor trip the Reactivity Alert feature of the SPOS actuates. What does this indicate? (0.5)
d. What is automatically displayed on the SPOS whenever a reactor trip occurs (i.e., how does the SPOS respond to a trip)? (0.5)
END OF CATEGORY 3
15 CATEGORY 4 - PROCEDURES: NORMAL, ABNORMAL, EMERGENCY AND RADIOLOGICAL CONTROL (25.0) 4.01 a. List the Immediate Actions that are common (identical) for the four Runback APs:
Loss of Booster Pump AP-540 Loss of Main Feed Pump; AP-541 Asymmetric Rod AP-542 Loss of One RCP AP-543 (1.0)
b. List the additional Immediate Actions for AP-541 " Loss of Main Feed Pump Runback." (1.0)
c. Match the runback condition with the approximate power level at which you expect the plant to stabilize. (1.0) i Booster Pump a. 75%
11 Main Feed Pump b. 70%
iii Asymmetric Rod c. 60%
iv One RCP d. 55%
e. 50%
4.02 An Immediate Action of AP-555, " Continuous Control Rod Withdrawal" is the following: .
3. Stop rod withdrawal:
a. Transfer rod (s) to alternate power supply. <
a. Assume the affected rod (s) are in Group 7. List the steps required to transfer the rod (s) to an alternate power supply. (2.0)
b. What are the Remedial Actions associated with Immediate Action (3) above? (1.0) 4.03 During periods when the reactor vessel head is removed, DHV-3, OHV-4 and DHV-41 must be open.
a. List two administrative and/or physical controls that are used to ensure these valves remain open. (1.0)
b. What are these actions intended to prevent? (1.0)
16 4.04 Fill in the following blanks with regard to containment access during Mode 1 operation.
a. Prior to any containment entry, personnel must (0.5) obtain a (Form) and have it signed by (Title) .
b. Crew size will be a minimum of (number) (0.5) personnel and the maximum time in the containment building will be limited to (time)
c. In the event that there are any personnel in (0.5) the containment building and the reactor trips (acticn to be taken) .
4.05 ICS procedure, OP-501 states in part, "If operating signal
[MC] source malfunctions make signal source transfer necessary, transfer to another signal source should be done..."Which one of the following CORRECTLY completes this statement? Assume the ICS has not responded to the malfunctioning signal. (1.0)
a. immediately after placing the affected ICS station in HAND.
b. immediately, regardless of ICS operating mode. .
c. only after checking the computer for a valid alternate signal and placing the affected ICS station in HAND.
d. only af ter checking the computer for a valid alternate signal; affected ICS station may be in HAND or AUTO.
4.06 The first Immediate Action of AP-380, " Engineered Safeguards System Actuation," is to:
1. Verify valid actuation:
RC pressure <1500 psig or ManuaT actuation What are the Remedial Actions associated with this step? (1.5) 4.07 Engineered Safeguards has actuated due to low RC prassure.
a. When are you required to stop the Reactor Coolant Pumps? (1.0)
b. Under what conditions (according to the Remedial Actions of AP-380) should the RCPs be kept running? (1.0)
17 4.08 OP203, Step 6.2.15 states that "When T(ave) is 57911 F and unit load demand >15%, place Reactor Demand and Diamond Station in Auto." Which station should be placed in auto first? (0,5) 4.09 OP 204, Power Operation, Section 2.0 states that "The expected various parametric system responses for reactor coolant (RC) and steam supply systems are given below. Also included are allowable deviations." Assuming that the reactor is at 50 percent power, what are the expected responses and allowable deviations for the folicwing parameters?
a. RC pressure (.25)
b. RC temperature (average) (.25)
c. RC temperature (inlet) (.25)
d. RC temperature (outlet) (.25)
e. OTSG Outlet Pressure (.25)
f. OTSG Outlet Steam Temperature (.25) 4.10 Fill in the following as stated in OP-401, Core Flooding System.
a. CFV-5 and CFV-6 must be and their breakers in the posit ion; breaker when reactor coolant (RC) is greater than 750 psig. (.75)
b. CFV-5 and CFV-6 must be and their breakers in the position when RC pressure is less than 625 psig. (0.5)
c. Core Flood Tank (CFT), temperature must be above *F before pressurizing the tanks. (.25) l
18 4.11 Which one of the following " Radiation Area" definitions means
[MC] the same as that given in RP-101, " Radiation Protection Manual"? (1.0)
a. any area where the dose rate exceeds five mrem /hr or where, in any five (5) consecutive day period, exceeds 100 mrem /hr at any time.
b. any accessible area where a major portion of the body could exceed a dose of five mrem in any one (1) hour, or in any five (5) consecutive days a dose in excess of 100 mrem.
c. any accessible area where any portion of the body could exceed a dose rate of five mrem /hr or where, in any five (5) consecutive day period, could exceed a dose rate of 100 mrem /hr at any time.
d. any area where the dose rate to any portion of the body could exceed a dose of five mrem in any one (1) hour, or in any five (5) consecutive days a dose in excess of 100 mrem.
4.12 TRUE or FALSE: An operator must be stationed at RCV-5 (pressurizer vent valve) to accomplish venting the pressurizer in accordance with OP 202, Plant Heatup. (0.5 4.13 OP-210, Reactor Startup requires a calculation of estimated critical rod position or estimated critical boron concentration.
What are the limits placed on each in terms of % Ak/k if:
a. pulling rods to critical (0.5)
b. deborating to critical (0.5) 4.14 The Immediate Actions of AP-460," Steam Generator Isolation Actuation" call for the operator to ensure valves on affected OTSG(s) are closed and selected closed. Assume a steam line break on OTSG 'A'. List these required valves by name or number. (2.0)
19 4.15 List the OTSG(s) that should be fed, according to the EFW logic system, for each of the six conditions below: (1.5)
OTSG OTSG OTSG PRESSURE PRESSURE FE0 DIFFERENCE A-B A B 100 <600 <600 (1)
-100 <600 <600 (2)
-99 to 99 <600 <600 (3)
N/A >600 >600 (4)
N/A >600 <600 (5)
N/A <600 >600 (6) 4.16 AP-530, " Natural Circulation", gives instructions concerning the symptoms and response to steam voids in the RCS. In order to reduce RC void volune: (choose the correct bracketed words),
a. RC temperature should be [ lowered], [ stabilized] [ raised] (0.5)
b. RC pressure should be [ lowered] [ stabilized] [ raised] (0.5)
c. Pressurizer level should be observed to be [ decreasing]
[ increasing] (0.5)
END OF CATEGORY 4
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ANSWERS (CATEGORY 1) 1.1 d (1.0)
Ref: NUS Module 3, Section 10.3 1.2 b (1.0)
Ref: CR Lesson Plan RQ-84-7E Degraded Core Recognition and Mitigation 1.3 a. Increase (0.5)
b. Decrease (0.5)
c. Increase (0.5)
d. No effect (0,5)
Ref: CR3 HTFF, pg 158 & 159 1.4 a. Higher (more Xenon) (0.5)
b. Lower (less negative than used in calc.) (0,5)
c. Higher (Tave increases, more neg, reactivity) (0.5)
d. No change (no effect on Tave) (0.5)
Ref: NUS Manual 3, Section 12.5 1.5 a.
b.
c.
Larger Longer Constant (1[
Ref: Westinghouse Reactor Physics, Section I-4 1.6 b (1.0)2 Ref: Thermo & Heat Transfer Manual, Reactor Heat Transfer and Thermal Hydraulics Section 1.7 a. (i) loop A= 42% loop B = 105% 1.0
b. (iii) loop A = 14.3% loop B = 35%
Ref: Integrated Control System; Handout; B&W, pp IV-4 & 5 ((l.6 1.8 b (1.0)
Ref: General Physics, HT & FF, pg 328 1.9 d (1.0)
Ref: NUS Manual 3, Section 5.3 1.10 (Topreventrapidanderraticchangesinpressurizer (1.0) levelfromoccurring)duetobubbleformation in the '
vessel head.
Ref: HTFF, CR-3 Draft Manual 1.11 b (1.0)
Ref: Hydrogen Recombiner, Lesson Plan 83-08-21-01, pg 6 1.12 c (1.0)
Ref: NUS Manual 3, Section 5.2
. . l
. 2 1.13 a. Inserted (0.5)
b. Inserted (0.5)
Ref: APSR Integral worth curve at 0% FP, AR0 1.14 a. Pressure boundary (0.5)
b. DNBR (0.5)
c. DNBR (0.5)
d. DNBR (0.5)
Ref: T.S. 2.1, Safety limits bases '
1.15 a. Increase (0.5)
b. Decrease (0.5)
c. Increase (0.5)
d. Increase (0.5)
Ref: NUS Module 3, Section 8.4 1.16 a. More (0.5)
b. Less (0.5)
Ref: NRC B&W System Manual, p. 8.1-8 1.17 a. Decreases +P (0.5)
b. Increases tTavg -P (0.5)
c. Remains constant (0.5)
d. Decreases +P (0.5)
Ref: NUS Module 3 1.16 Greater than (0.5)
Ref: Technical Specifications 1.0, Definitions SP421 Shutdown Margin 1.19 a. Increase (0.5)
b. Decrease (0.5)
Ref: NUS Module 3, Section 9.2
3 CATEGORY 2 (Answers) 2.01 2 - are located on the Remote Shutdown (0.5)
Panel - 2nd floor of Control Complex outside of
'B' 4ky Switch Gear Room 1 - inside 'A' 4kv ES Switch Gear Room -(0.25) 1 - inside 'B' 4ky ES Switch Gear Room (0.25)
Ref: Remote Shutdown Panel, MAR Training, 77-07-01, pg 1 2.02 c (1.0)
Ref: Remote Shutdown Panel, MAR Training, 77-07-01, pg 1 2.03 True (0.5)
Ref: Remote Shutdown Panel, MAR Training, 77-07-01, pg 89 2.04 (1) provide oil to the R4 pump / turbine if both AC pumps should (0.5) fail to allow safe shutdown of the FW pump (2) lube oil pressure 10 psig decreasing (0.5)
Ref: STM 27-22 1
2.05 Answer: 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months (0.5) <
Ref: TS B 3/4 7-2 2.06 Answer: This is the core lift interlock 9 less than 500'F, f!'O the density of water could be sufficient (0,5) such that force exerted by inlet coolant could lift core components. (0.5)
(Hydraulic lift considerations)
Ref: OP302, RC Pump Operation 2.07 Answer: To ensure that during a large break LOCA, CFT (1.0) injection will occur immediately after " blowout" of water from the lower part of the core.
Ref: STM-4-6 2.08 Answer: a. low exhaust hood temperature (1.0)
Ref: STM 27-72
4
'2.09 Answer: False, No auto starts (0.5),
Ref: STM 30-2 2.10 a. False (0.5)
b. True (0.5)
c. False (0.5)
d. False (0.5)
Ref: STM 23-7, OP-502 p.3, OP-508 2.11 Answer: (1) (closes WDV 439)
(waste gas discharge auto control valve) (0.5).
(2) (closes WDV 393, 394 and 395)
(waste gas decay tank outlet to recycle valve) ( 0.'5 )
Ref: STM 41-4 2.12 Answer: c. gland condenser (1.0)
Ref: STM 34-3 2.13 Answer: a. Modulating solenoid valves that use an increasing DC current opposing spring pressure. (0.5) <
b. Fail in full open position on 0 loss of power. (0.5) ;
c. No provisions for any local or manual control (0.5)
Ref: Lesson: EFV and EFIC; AN0-113, p. 8 & 9 -
?.14 Answer: EFV-1 and EFV-2 are interlocked such that they can be open only if at least one of the two DC powered condenser vacuum breakers is open. (1.0)
Ref: Lesson: Emergency Feedwater and EFIC, ANO-113, pg 2 2.15 Answer: a. reactor auxiliary 480 Bus A & B (0.25)
b. 3 (0.25) g d. .. 2 4160V ES Bus B MCC-3B el:
(02)
(0.25) d eo v T%d k % Tta Ref: STM 2-120, OP 202 step 6.3.1, AP 770 step 5 2.16 Answer: Decay heat closed cooling water (1.0)
Ref: STM 5-1 2.17 Answer: c. potassium sulfate (1.0)
Ref: STM 5-2
5 2.18 Answer: by admitting water to the upper section of the steam generator thereby cooling the tubes and primary water near the top of the S/6. (1.0)
Ref: STM 2-55 2.19 Answer: (1) after 150 minutes idle time (0.5)
(2) after 25 minutes running time (0.5)
Ref: STM 2-105 2.20 Answer: Installation of gates in the separation wall with inflatable seals pressurized from station air. (1.0)
Ref: STM 21-91 2.21 Answer: 15 hours1.736111e-4 days 0.00417 hours 2.480159e-5 weeks 5.7075e-6 months (0.5)
Ref: OP 404, step 4.2 2.22 Answer False (0.5)
Ref: OP 605 Section 13.3 2.23 Answer: Hydrazine chemical reactive with the resin could result in chloride release. (1.0)
Ref: OP 403, Sec 4.7.10 2.24 MCC 3A3 119' Elev (Aux Bldg) in Corridor near MCC 3A2 - Directly East of Spent Fuel Ponis (0.5)
MCC 383 95' Elev (Aux Bldg) Outside MVP area (0.5)
Ref: Lesson No. MAR 80-05-14-03
6 CATEGORY 3 ANSWERS 3.01 1. 50 psig (0.5)
2. 125 psig (0.5)
3. 50 psig (0.5)
4. O ps1 9oS5Dfug w (0.5)
Ref: STM CH 504, pg 49 & 50 3.02 a. No runback. (0.5) Load limit for 3-RCP's is 75% (page 12) (0.5)
b. FW will reratio. (0.5) Total FW demand signal is modified by delta between Loop A and Loop B RCS flow (see diagram page 72) (0.5)
Ref: STM CH 504, pages noted above.
3.03 a. SG/Rx Master cc LALD W - (pg 114) (0.5)
b. feedwater flow / level (pg 116) (0,5)
c. Iow load block valve (pg 117) (0.5) d.(1) low load control e Lbt VMv6, (pg 122) (0.5)
(ii) AP/ flow w (pg 122) (0.5)
Ref: STM CH 504, pages noted above 3.04 1. FW demand reaches 45% decreasing b'O)
2. Reactor trips
3. Main FW pump trips
4. EFIC isolation actuation occurs (Cka%d A gr_ CkmAL} w;
5. FWV-28 (crosstie not shut)
(Any 4 of 5; 0.5 each.)
Ref: OP-504, Rev. 12, pg. 9 3.05 c (1.0)
Ref: power System Operation, R.H. Miller, pg. 17 3.06 a. 1-F 2-0 3-A 4-C 5-E (0.3 each; 1.5 Total)
b. Upon DH pump trip, the DH v=lve will remain in its current position until changed by - operator (pg 5) (0.5)
c. BS valve control units have an additional control feature, there is a Remote (R) and a Local (L) setting on the lef t side of the display unit. Remote position - fixed voltage signal corres-ponding to 1550 gpm is sent to valve controller. (1.0)
Ref: MAR Training: 83-09-03-01, pg 5
s 7
W 3.07 a. 1. HPI Block 3 and Block actuated on 2 out of 3 channels (RC-1, RC-2, RC-3) or (0.5)
2. HPI bypassed after an actuation on 2 out of 3 channels (RC-1,RC-2,hC-3) (0.5)
b. 30 psig signal [2 of 3 channels RB-4, RB-5, RB-6] (0.5)
c. 1. 2 new reset pushbuttons on ESF-A&B sections of main control board (0.5)
2. If HPI is bypassed and the associated ES 4160V bus UV relays actuate, the permit will be automatically reset. (0.5)
3. If HPI is bypassed and is then reactuated by either LPI or RB 150 and COOLING, the permit will automatically be reset. (0.5)
Ref: MAR TRAINING, #82-05-01-01, ES LOGIC MODIFICATION, pg 2 & 3 3.08 a. True (0.5)
b. False (parallel) (0.5)
c. True (0.5)
Ref: Lesson No. 80-11-48-01/02/03 3.09 a. Ensures that the TBV's remain closed on a loss of power. (1.0) 1
b. On loss of CW pumps or low vacuum, the ICS will close the TBV's. (Circuitry in the ICS that shifted header pressure control to A0V's [for loss of CW pumps and low vacuum] has
been removed.) (1.0)
Ref: Lesson No. 77-07-01-11 3.10 a. controlled bleed off temp 3170 F (verified),
high seal stage pressure drop 3 2/3 RCS pressure g 4p(.25) i WL
(.25)
b. Total seal outflow exceeds 2.5 gpm bj (.25) and is rapidly increasing g WY q#Y M (.25)
Ref: OP 302, page 5 3.11 a. Reactor power must be >20% for auto initiation on loss of both main FW pumps (pg. 14) (0.5)
b. 1 of 2 Taken Twice logic - Only one bus relays are energized (pg 13 - Fig. SA) (0,5)
. - EFIC is manually bypassed (loss of all RCP initiation) when reactor power is <18%. (pg 14) --(0.5) 'N
d. Initiation of EFW requires HPI actuation of Both A & B ESAS channels. (pg 14) (0.5)
Ref: ANO-113 Emergency FW & EFIC pp-noted above.
t g
3.12 a. True (0,5)
b. False (0.5)
Ref: OP 502 4.25 & 4.26 3.13 a. Highest of 4 Power Range NI's (0.5)
b. Average of 5 highest incore readings (12 incore inputs into SPDS) (0.5)
c. Source Range count rate >1000 cps, (.25) and all rods are in. (.25)
d. The SPDS display will automatically switch to the Post-Trip Screen (.25) with the history trace on (.25)
Ref: MAR Training, SPDS
1
, s 9
CATEGORY 4 - ANSWERS 4.01 a. 1. Ensure turbine runback
2. Ensure RC stable (1.0)
NOTE: All but AP-542 say " Ensure control rods inserting",
AP-542 says " Ensure NI power lowering."
b. Ensure: (1) affected MFP tripped (2) OPEN - FWV-28 (cross-tie)
(3) CLOSE0 - FWV-29 and FW-30 (4) Ensure control rods inserting (1.0)
c. 1 - 55% -d 11 - 55% -d 111 - 60% -c iv - 70% -b (1.0) 4.02 NOTE: OP-502 Step 12.1 says to refer to Section 7.1. This section addresses Safety Group Transfer from DC Hold to Auxiliary.
\.%%O kO9W W ,O
a. lect: All (Optional) g g Qc % aovp le -
(
E ' ~
Select: Aux (.2) Nd hW Select: up desir (.2) G\uk Stq-C:t.
Oepress Trans R et (.2) s,gg ge,w Select: Jog (.2) 7 g q Select: Cla (.2)
Press: ual Trans (.2) 3 5de C.%?
Press: Clamp Rei (.2) 4. Skd phTDMimt.
Press- Group 2) C 5.\cd Ch9 RGt.rMS Se ct: Run, if desired ( u % d- G,aovP Ref:
1 OP-502,Rev.17, Step 7.1.1throughg.1q.0 k
Rut 4 L
)
hud)
b. Trip Reactor AND (.5) go to AP-580 (.5) 4.03 a. 1. Breaker control handle placed in (0.5)
" Lock-Reset" position i 2. Control will be under Shift Supervisor and (0.5) the breakers and valves shall be blue-tagged
b. In order to prevent isolation of the OH systems (0.5) due to a spurious 284 psig signal (0.5)
Ref: OP-404, Rev. 53, pg. 4.
10 4.04 a. Radiation Work Permit (.25)
Shift Supervisor (.25)
b. 2 (.25)
I hr (.25)
c. Sound containment evacuation alarm. (0.5)
Ref: OP-417, Rev. 38 pgs 4 and 36 4.05 Answer: b (1.0)
Ref: OP-501, Rev. 8, pg. 3.
4.06 1. Bypass ES Actuation (0.5)
2. Return ES Equipment to Standby status (0.5)
3. Go to VP-580 (0.5)
Ref: AP-380, Rev. 04, pg. 3.
4.07 a. If subcooling margin is inadequate (1.0)
> 1500 psig 20 F 31500psig 53*F
b. If all RCPs have not been stopped within (1.0) two minutes, they must be kept running
)
Ref: AP-380, Rev. 04, pg. 4. 1 4.08 Answer: Diamond (0.5)
Ref: OP-203, pg. 12 4.09 Answer: a. 2155!100%pitg (.25)
b. 579 1 3.5'F (.25)
c. 568 1 3.5'F (.25)
d. 590 1 3.5 F (.25)
e. 8^1 : 9 pig 900 E lD P6Tr (.25) 588 1 5*F (.25)
>f.
Ref: OP-204, Section 2.0 4.10 a. Open, Locked Reset, Locked (.75)
b. Closed, Locked Reset, (0.5)
c. 69 (.25)
Ref: OP-401 hbe I 20Fe i d ',i f a sedgM aud v
wn1% m%
e 11 4.11 Answer: b (1.0)
Ref: RP-101, p. 5 4.12 Answer: True (0.5)
Ref: OP-202, Step 6.3.2 4.13 a.
1% Delta K/K (0.5)
b. . 1% Delta K/K (0.5)
Ref: OP-210, Enclosures 3 and 4 4.14 OTSG A MSV-411 & 412 (MSIVs)
FWV-30 (MBV)
FWV-31 (LLBV)
FWV-36 (SUBV)
FWV-28 (Cross-tie)
FWV-14 (FWp Suction)
FWV-35 (EBV)
- 'OTE: Step 3 - MSV-5 P NOTE: Step 4 - Ensure Closed MSV-9 & 10 (TBVs)
MSV-25 (A0V)
AW, cu m cy crrst A (0.2 ea)
Ref: AP-460, Rev.pg02, Q. 2oTgc, g gg y 4.15 (1) -
A (2) -
B (3) -
A, B (4) -
A, B (5) -
A (6) -
B (0.25 ea)
Ref: AP-460, Rev. 02, pg. 5.
4.16 a. Stabilized (0.5)
b. Raised (0.5)
c. Decreasing (0.5)
Ref: AP-530, Rev. 04, pg. 14.

@@ Line 42: / Line 42: @@
    !                                           D. P. Falconer, NPC Region II
 * Chief Examiner
-: 3.           Examination Review At the conclusion of the written examinations, the examiners provided the facility with a copy of the written examinations and answer keys for review. The following comments were provided by the licensee by letter dated November 26, 1985,
+: 3.           Examination Review At the conclusion of the written examinations, the examiners provided the facility with a copy of the written examinations and answer keys for review. The following comments were provided by the licensee by {{letter dated|date=November 26, 1985|text=letter dated November 26, 1985}},
 : a.                      Reactor Operator Examination (1) Question 1.5(c)
 The answer on the key is correct, however, an increasing positive startup rate would also be indicative of a supercritical reactor.

ML20137Y281: Difference between revisions

Latest revision as of 05:07, 13 December 2021

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8.1 Answer

8.2 Answer

8.3 Answer

8.4 Answer

8.6 Answer

8.7 Answer

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ML20137Y281: Difference between revisions

Latest revision as of 05:07, 13 December 2021

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SUMMARY

8.1 Answer

8.2 Answer

8.3 Answer

8.4 Answer

8.6 Answer

8.7 Answer

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